Text

2014 Annual Radiological Environmental Operating Report
	ML15147A606
Person / Time
Site:	Limerick
Issue date:	04/30/2015
From:	; Teledyne Brown Engineering Environmental Services
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
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ML15147A604	List: LG-15-048, 2014 Annual Radiological Environmental Operating Report; ML15147A605;
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50-352 50-353 LIMERICK GENERATING STATION UNITS 1 and 2 Annual Radiological Environmental Operating Report 1 January Through 31 December 2014 Prepared By Teledyne Brown Engineering Environmental Services Exelon Generation April 2015

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Table Of Contents I. Sum m ary and Conclusions..............................................................................................

1 II. Introduction............................................................................................................

3 A. Objectives of the REM P................................................................................

3 B. Im plem entation of the O bjectives...................................................................

4 I1l. Program Description.................................................................................................

4 A. Sam ple Collection..........................................................................................

4 B. Sam ple Analysis.............................................................................................

6 C. Data Interpretation..........................................................................................

6 D. Program Exceptions.......................................................................................

8 E. Program Changes..........................................................................................

8 F. Com pliance to 10CFR190 Lim its.....................................................................

8 IV. Results and Discussion............................................................................................

9 A. Aquatic Environm ent.....................................................................................

9

1. Surface W ater......................................................................................

9

2. Drinking W ater...................................................................................

10

3. Fish...................................................................................................

10

4. Sedim ent.............................................................................................

11 B. Atm ospheric Environm ent............................................................................

12

1. Airborne............................................................................................

12

a. Air Particulates........................................................................

12

b. Airborne Iodine.......................................................................

12

2. Terrestrial..........................................................................................

13

a. M ilk...........................................................................................

13

b. Broad Leaf Vegetation...........................................................

13 C. Am bient Gam m a Radiation..........................................................................

14 D. 10 CFR 20.2002 Perm it Storage Area.........................................................

14 E. Independent Spent Fuel Storage Area........................................................

15 F. Land Use Survey..........................................................................................

15 G. Errata Data....................................................................................................

15 H. Summary of Results - Inter-Laboratory Comparison Program....................

16 V. References...................................................................................................................

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Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Appendix B Tables Table B-1 Table B-2 Table B-3 Figures Radiological Environmental Monitoring Program Annual Summary for the Limerick Generating Station, 2014 Location Designation, Distance & Direction, and Sample Collection &

Analytical Methods Location Designation and Identification System for the Limerick Generating Station Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2014 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2014 Environmental Sampling Locations Within 5,280 Feet of the Limerick Generating Station, 2014 Environmental Sampling Locations Between 5,280 and 26,400 Feet from the Limerick Generating Station, 2014 Environmental Sampling Locations Greater Than 26,400 Feet from the Limerick Generating Station, 2014 Data Tables and Figures - Primary Laboratory Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2014 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2014 Figure B-1 Figure B-2 Figure B-3 Appendix C Tables Table C-1.1 Table C-1.2

Table C-11.1 Table C-11.2 Table C-11.3 Table C-11.4 Table C-111.1 Table C-IV. 1 Table C-V.1 Table C-V.2 Table C-V.3 Table C-VI. 1 Table C-VII. 1 Table C-VII.2 Table C-VIII.1 Table C-IX.1 Table C-IX.2 Table C-IX.3 Fi-gures Figure C-1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2014 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2014 Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2014 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2014 Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Limerick Generating Station, 2014 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Limerick Generating Station, 2014 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2014 Monthly and Yearly Mean Values of Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2014 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2014 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Limerick Generating Station, 2014 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2014 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2014 Concentrations of Strontium and Gamma Emitters in Broad Leaf Vegetation Samples Collected in the Vicinity of Limerick Generating Station, 2014 Quarterly DLR Results for Limerick Generating Station, 2014.

Mean Quarterly Dosimeter Results for the Site Boundary, Middle and Control Locations for Limerick Generating Station, 2014 Summary of the Ambient Dosimetry Program for Limerick Generating Station, 2014 Mean Monthly Total Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of LGS, 1982 - 2014

Figure C-2 Figure C-3 Figure C-4 Figure C-5 Figure C-6 Appendix D Tables Table D-1.1 Table D-1.2 Table D-1.3 Table D-1.4 Table D-1I.1 Table D-II.2 Table D-1Il.1 Figures Figure D-1 Figure D-2 Mean Annual Cs-137 Concentrations in Fish Samples Collected in the Vicinity of LGS, 1982 - 2014 Concentrations of Cs-1 37 in Sediment Samples Collected in the Vicinity of LGS, 1982 - 2014 Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 1982 - 2014 Mean Weekly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 2014 Mean Quarterly Ambient Gamma Radiation Levels (DLR) in the Vicinity of LGS, 1985 - 2014 Data Tables and Figures - Comparison Laboratory Concentrations of Total Gross Beta in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2014 Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2014 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2014 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2014 Concentrations of Gross Beta in Air Particulate and 1-131 in Air Iodine Samples Collected in the Vicinity of Limerick Generating Station, 2014 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2014 Concentrations of 1-131 by Chemical Separation and Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2014 Comparison of Monthly Total Gross Beta Concentrations in Drinking Water Samples Split Between ENV and TBE, 2014 Comparison of Weekly Gross Beta Concentrations in Air Particulate Samples Collected from LGS Collocated Locations 11S1 and 11S2, 2014

Appendix E Tables Table E-1 Table E-2 Table E-3 Table E-4 Table E-5 Appendix F Appendix G Inter-Laboratory Comparison Program Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2014 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2014 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2014 ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2014 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2014 Errata Data Annual Radiological Groundwater Protection Program Report (ARGPPR)

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1.

Summary and Conclusions In 2014, the Limerick Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 147 curies of noble gas, fission and activation products and approximately 47 curies of tritium.

The dose from both liquid and gaseous effluents was conservatively calculated for the Maximum Exposed Member of the Public. The results of those calculations and their comparison to the allowable limits were as follows:

Gaseous and liquid radiation doses to members of the public at the highest dose receptor Effluent Applicable Estimated Age Location

% of Limit Unit Organ Dose Group Applicable Limit Noble Gas Gamma - Air Dose 5.99E-03 All Nearest Residence 3.00E-02 20 mRad Noble Gas Beta - Air Dose 3.69E-03 All Nearest Residence 9.23E-03 40 mRad Noble Gas Total Body (Gamma) 5.64E-03 All Nearest Residence 5.64E-02 10 mrem Noble Gas Skin (Beta) 9.28E-03 All Nearest Residence 3.09E-02 30 mrem

Iodine, Particulate, Bone 1.40E-00 Child Vegetation 4.67E-00 30 mrem Tritium & C-14 Liquid Total Body 4.93E-04 Adult LGS Outfall 8.22E-03 6

mrem Liquid GI-Ui 5.59E-04 Adult LGS Outfall 2.80E-03 20 mrem The calculated doses, from the radiological effluents released from Limerick, were a very small percentage of the allowable limits.

This report on the Radiological Environmental Monitoring Program conducted for the Limerick Generating Station (LGS) by Exelon covers the period 1 January 2014 through 31 December 2014. During that time period, 1332 analyses were performed on 1005 samples.

Surface and drinking water samples were analyzed for concentrations of tritium and gamma emitting nuclides. Drinking water samples were also analyzed for concentrations of 1-131 and total gross beta. No fission or activation products were detected. No 1-131 was detected. Gross beta activities detected were consistent with those detected in previous years.

Fish (predator and bottom feeder) and sediment samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected in fish.

Sediment samples collected below the discharge had Cesium-1 37 concentrations that were consistent to those from previous years. No other station produced fission or activation products were found in sediment. The calculated dose to a teenagers skin and whole body was 4.67E-04 mrem and 4.01 E-04 mrem, respectively. This dose represents 2.34E-03% and 6.68E-03%,

respectively of the 10 CFR Part 50, Appendix I dose limits.

1

Air particulate samples were analyzed for concentrations of gross beta and gamma emitting nuclides. Gross beta and cosmogenic Be-7 were detected at levels consistent with those detected in previous years. No fission or activation products were detected.

High sensitivity 1-131 analyses were performed on weekly air samples. All results were less than the minimum detectable concentration.

Cow milk samples were analyzed for concentrations of 1-131 and gamma emitting nuclides. Concentrations of naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were found.

Broad leaf vegetation samples were analyzed for strontium and gamma emitting nuclides. Concentrations of naturally occurring Be-7 and K-40 were detected.

Radium-226 was found in 10 of 45 samples. Strontium-90 was found in 10 of 45 samples. Thorium-228 was found in 1 of 45 samples. Radium-226 and Thorium-228 were detected in low concentration just above the MDC (minimum detectable concentration). Strontium-90 activity can be attributed to historical nuclear weapons testing and Chernobyl accident.

Review of the gamma spectroscopy results from the surface water samples located at the Limerick intake (24S1) and downstream of the 1 OCFR20.2002 permitted storage area showed no evidence of offsite radionuclide transport from the 2002 permitted storage area.

Environmental ambient gamma radiation measurements were performed quarterly using DLRs (Dosimeter of Legal Record). Levels detected were consistent with those observed in previous years.

A review of the dosimetry data for the nearest residence to the Independent Spent Fuel Storage Installation (ISFSI) indicates no direct dose was received.

A radiological groundwater protection program (RGPP) was established in 2006 as part of an Exelon Nuclear fleetwide assessment of potential groundwater intrusion from the operation of the Station. In 2014, well water samples were analyzed for tritium, Sr-89, Sr-90, gross alpha, gross beta, and gamma emitters.

Surface water samples were analyzed for tritium, and gamma emitters.

Precipitation water samples were analyzed for tritium.

Most of the tritium values for well water, surface water and precipitation water were less than the lower limit of detection of 200 pCi/L. Results and Discussion of groundwater samples are covered in Appendix G.

In assessing the data gathered for this report and comparing these results with preoperational data, it was concluded that the operation of LGS had no adverse radiological impact on the environment.

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II.

Introduction The Limerick Generating Station (LGS), consisting of two 3,515 MWt boiling water reactors owned and operated by Exelon Corporation, is located adjacent to the Schuylkill River in Montgomery County, Pennsylvania. Unit No. 1 went critical on 22 December 1984. Unit No. 2 went critical on 11 August 1989. The site is located in Piedmont countryside, transversed by numerous valleys containing small tributaries that feed into the Schuylkill River. On the eastern river bank elevation rises from approximately 110 to 300 feet mean sea level (MSL). On the western river bank elevation rises to approximately 50 feet MSL to the western site boundary.

A Radiological Environmental Monitoring Program (REMP) for LGS was initiated in 1971. Review of the 1971 through 1977 REMP data resulted in the modification of the program to comply with changes in the Environmental Report Operating License Stage (EROL) and the Branch Technical Position Paper (Rev.

1, 1979). The preoperational period for most media covers the periods 1 January 1982 through 21 December 1984 and was summarized in a separate report. This report covers those analyses performed by Teledyne Brown Engineering (TBE), Mirion Technologies and Environmental Inc. (Midwest Labs) on samples collected during the period 1 Janua.ry 2014 through 31 December 2014.

On 6 July 1996 a 1 OCFR20.2002 permit was issued to Limerick for storage of slightly contaminated soils, sediments and sludges obtained from the holding pond, cooling tower and spray pond systems. These materials will decay to background while in storage. Final disposition will be determined at Station decommissioning.

On 21 July 2008 an ISFSI pad was put into service. The ISFSI is dry cask storage, where spent nuclear fuel is stored.

A.

Objective of the REMP The objectives of the REMP are to:

1.

Provide data on measurable levels of radiation and radioactive materials in the site environs.

2.

Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure.

3

B.

Implementation of the Objectives The implementation of the objectives is accomplished by:

1.

Identifying significant exposure pathways.

2.

Establishing baseline radiological data of media within those pathways.

3.

Continuously monitoring those media before and during station operation to assess station radiological effects (if any) on man and the environment.

Ill.

Program Description A.

Sample Collection.

Samples for the LGS REMP were collected for Exelon Nuclear by Normandeau Associates, Inc. (NAI). This section describes the general collection methods used by NAI to obtain environmental samples for the LGS REMP in 2014. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-1 through B-3, Appendix B. The collection procedures used by NAI are listed in Table B-3.

Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, drinking water, fish, and sediment.

Two-gallon water samples were collected monthly from composite samplers located at two surface water locations (133B1 and 24S1) and four drinking water locations (15F4, 15F7, 16C2, and 28F3). Control locations were 24S1, and 28F3. All samples were collected in new unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising of the flesh of two groups, bottom feeder (catfish/north hognose sucker/white suckers) and predator (sunfish/bass/rock bass/trout), were collected semiannually at two locations, 16C5 and 29C1 (control). Sediment samples composed of recently deposited substrate were collected at three locations semiannually, 16B2, 16C4, and 33A2 (control).

Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, and milk. Airborne iodine and particulate samples were collected and analyzed weekly at seven locations (6C1, 10S3, 11S1, 13S4, 14S1, 15D1, and 22G1). The control location was 22G1. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis.

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Terrestrial Environment Milk samples were collected biweekly at four locations (18E1, 19B1, 23F1, and 25C1) from April through November, and monthly from December through March. One additional location (36E1) was sampled quarterly.

Locations 36E1 and 23F1 were controls. All samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite, and shipped promptly to the laboratory.

Broad leaf vegetation was collected monthly at three locations (11 S3, 13S3, and 31G1 ). The control location was 31G1. Five different kinds of vegetation samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.

Ambient Gamma Radiation Direct Radiation measurements were made using thermoluminescent dosimeters. The DLR locations were placed on and around the LGS site as follows:

A site boundary ring consisting of 16 locations (36S2, 3S1, 5S1, 7S1, 10S3, 11S1, 13S2, 14S1, 18S2, 21S2, 23S2, 25S2, 26S3, 29S1, 31S1, and 34S2) near and within the site perimeter representing fence post doses (i.e., at locations where the doses will be potentially greater than maximum annual off-site doses) from LGS releases.

An intermediate distance ring consisting of 16 locations (36D1, 2E1, 4E1, 7E1, 10E1, 10F3, 13E1, 16F1, 19D1, 20F1, 24D1, 25D1, 28D2, 29E1, 31 D2, and 34E1) extending to approximately 5 miles from the site designed to measure possible exposures to close-in population.

The balance of eight locations (5H1, 6C1, 9C1, 13C1, 15D1, 17B1, 20D1, and 31 D1) representing control and special interests areas such as population centers, schools, etc.

The specific dosimetry locations were determined by the following criteria:

1.

The presence of relatively dense population;

2.

Site meteorological data taking into account distance and elevation for each of the sixteen-22 1/2 degree sectors around the site, where estimated annual dose from LGS, if any, would be most significant;

3.

On hills free from local obstructions and within sight of the vents (where practical);

4.

And near the closest dwelling to the vents in the prevailing downwind direction.

Two dosimeters were placed at each location in a PVC conduit located approximately three feet above ground level. The dosimeters were exchanged quarterly and sent to Mirion Technologies for analysis.

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10CFR20.2002 Permit Storage Area In 1996 the Limerick Generating Station received NRC approval to store slightly contaminated soils, sludges and sediments on site per the requirements of 10CFR20.2002. These materials will be stored until end of the site's renewed operating license. At that time the material will be evaluated along with the site for decommissioning. The area is approximately 1.5 acres in size and was evaluated to hold a maximum of 1.12E+06 cubic feet with no more than 7E+04 cubic feet added to the area in any single year. After each material placement on the 2002 pad, the area is graded and seeded to prevent erosion. Since all groundwater movement is to the river, the use of the REMP surface water sampling program is used as a check on potential groundwater movement from the pad.

Independent Spent Fuel Storage Installation (ISFSI)

The results from the dosimeter location 36S2 were used to determine the direct radiation exposure to the nearest residence from the ISFSI pad.

B.

Sample Analysis This section describes the general analytical methodologies used by TBE and Midwest Labs to analyze the environmental samples for radioactivity for the LGS REMP in 2014. The analytical procedures used by the laboratories are listed in Appendix B Table B-3.

In order to achieve the stated objectives, the current program includes the following analyses:

1.

Concentrations of beta emitters in drinking water and air particulates.

2.

Concentrations of gamma emitters in surface and drinking water, air particulates, milk, fish, broad leaf vegetation, and sediment.

3.

Concentrations of tritium in surface and drinking water.

4.

Concentrations of 1-131 in air, milk, and drinking water.

5.

Ambient gamma radiation levels at various site environs.

C.

Data Interpretation The radiological and direct radiation data collected prior to LGS becoming operational was used as a baseline with which these operational data were compared. For the purpose of this report, LGS was considered operational at initial criticality. In addition, data were compared to previous years' operational data for consistency and trending. Several factors were important in the interpretation of the data:

6

1.

Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) is defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD is intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criteria for the presence of activity. All analyses are designed to achieve the required LGS detection limits for environmental sample analysis.

The minimum detectable concentration (MDC) is defined as above with the exception that the measurement is an after the fact estimate of the presence of activity.

2.

Net Activity Calculation and Reportingq of Results Net activity for a sample was calculated by subtracting background activity from the sample activity. Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity affecting a negative number. An MDC was reported in all cases where positive activity was not detected.

If no positive activity was detected, then gamma spectroscopy MDC results for each type of sample were grouped as follows:

For surface and drinking water twelve nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95, Nb-95, 1-131, Cs-134, Cs-137, Ba-140, and La-140 were reported.

For broad leaf vegetation eleven nuclides, Be-7, K-40, Mn-54, Co-58, Co-60, 1-131, Cs-134, Cs-137, Ra-226, Th-228, and Th-232 were reported.

For fish nine nuclides, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, 1-131, Cs-1 34, and Cs-1 37 were reported.

For sediment eight nuclides, Be-7, K-40, Mn-54, Co-58, Co-60, 1-131, Cs-1 34, and Cs-1 37 were reported.

For air particulate six nuclides, Be-7, Mn-54, Co-58, Co-60, Cs-1 34, and Cs-1 37 were reported.

For milk five nuclides, K-40, Cs-1 34, Cs-1 37, Ba-1 40, and La-140 were reported.

7

Means and standard deviations of positive results were calculated.

The standard deviations represent the variability of measured results for different samples rather than single analysis uncertainty.

D.

Program Exceptions For 2014 the LGS REMP had a sample recovery rate of 90%. Exceptions are listed below:

1.

Air sample from location 22G1 for the week of 02/24/14 - 03/2/14 was not available due to inadequate volume from a blown fuse (IR 1640093).

2.

Air sample from location 15D1 for the week of 06/16/14 - 06/23/14 was not available due to equipment malfunction (IR 2400170).

3.

Air sample from location 10S3 for the week of 10/13/14 - 10/20/14 was not available due to equipment malfunction (IR 2422722).

4.

Air samples from location 22G1 for the time frame of 07/07/14 -

09/29/14 was not available due to loss of power of underground wiring (IR 1689430). During this period of time another location was used, located in a least prevalent wind direction, to satisfy the requirements of a control location in the ODCM.

Each program exception was reviewed to understand the causes of the program exception. Sampling and maintenance errors were reviewed with the personnel involved to prevent recurrence. Occasional equipment breakdowns and freezing temperatures were unavoidable.

The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.

E.

Program Changes

1.

In September 2014, the air station 13S4 was added to the SE sector. See Appendix B for detailed location information.

F.

Compliance to 40CFR190 Limits A.

Dose to Members of the Public at or Beyond Site Boundary Per ODCM Control 6.2, the Annual Radioactive Effluent Release Report shall include an assessment of the radiation doses to the hypothetically highest exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources. The ODCM does not require population doses to be calculated. For 8

purposes of this calculation the following assumptions were made:

" Long term annual average meteorology X/Q and D/Q and actual gaseous effluent releases were used.

Gamma air dose, Beta air dose, Total Body and Skin doses were attributed to noble gas releases.

" Critical organ and age group dose attributed to iodine, particulate, carbon-14 and tritium releases.

100 percent occupancy factor was assumed.

Dosimetry measurements (minus background levels) obtained from the Radiological Environmental Monitoring Program for the nearest residence to the Independent Spent Fuel Storage Installation (ISFSI) was used to determine direct radiation exposure.

The highest doses from the critical organ and critical age group for each release pathway was summed and added to the net dosimetry measurement from nearest residence to the ISFSI for 40CFR190 compliance.

40 CFR 190 Compliance:

The maximum calculated dose to a real individual would not exceed 2.86E-01 mrem (total body), 1.41 E+00 mrem (organ), or 2.86 E-01 mrem (thyroid).

All doses calculated were below all ODCM and 40 CFR Part 190 limits to a real individual.

Table 1: 40CFR190 Compliance 40 CFR 190 Compliance Gaseous Effluents Noble Particulate, Liquid Net Direct

% of Total Applicable Limit Unit Gas lodone, C-14 Effluents Radiation Limit

& Tritium Total Body 5.64E-03 2.80E-01 4.93E-04 0.OOE+00 2.86E-01 1.15E+00 25 mrem Dose I _IIII Organ Dose 9.29E-03 1.40E+00 5.59E-04 0.OOE+00 1.41E+00 5.64E+00 25 mrem Thryoid Dose 5.64E-03 2.80E-01 4.55E-04 0.OOE+00 2.86E-01 3.82E-01 75 mrem IV.

Results and Discussion A.

Aquatic Environment

1.

Surface Water Samples were taken from a continuous sampler at two locations (13B1 and 24S1) on a monthly schedule. Of these locations only 13B1 located downstream, could be affected by Limerick's effluent releases. The following analyses were performed:

9

Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Appendix C, Table C-1.1). All results were below the required LLD.

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Appendix C, Table C-l.2). All nuclides were below the required LLDs.

2.

Drinking Water Monthly samples were collected from continuous water samplers at four locations (15F4, 15F7, 16C2, and 28F3). Three locations (15F4, 15F7, and 16C2) could be affected by Limerick's effluent releases. The following analyses were performed:

Gross Beta Samples from all locations were analyzed for concentrations of total gross beta (Appendix C, Tables C-11.1). The values ranged from 2.1 to 6.7 pCi/L. Concentrations detected were consistent with those detected in previous years (Appendix C, Figure C-1).

Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity. All results were below required LLD (Appendix C, Table C-11.2).

Iodine-131 Monthly samples were taken from all locations and analyzed for Iodine-131 activity (Appendix C, Table C-11.3). All results were below the required LLD.

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Appendix C, Table C-11.4). All results were below the required LLDs.

3.

Fish Fish samples comprised of bottom feeder (catfish/north hognose sucker/white suckers) and predator (sunfish/bass/rock bass/trout) were collected at two locations (16C5 and 29C1) in the spring and 10

fall season. Location 16C5 could be affected by Limerick's effluent releases. The following analysis was performed:

Gamma Spectrometry The edible portion of fish samples from both locations was analyzed for gamma emitting nuclides (Appendix C, Table C-111.1).

Naturally occurring K-40 was found at all stations and ranged from 3,123 to 5,702 pCi/kg wet and was consistent with levels detected in previous years. No other activity was detected and the required LLD was met. Though Cs-1 37 was not detected in 2014, historical levels of Cs-1 37 are shown in Appendix C, Figure C-2.

4.

Sediment Aquatic sediment samples were collected at three locations (16B2, 16C4 and 33A2) semiannually. Of these locations two, 16B2 and 16C4, could be affected by Limerick's effluent releases. The following analysis was performed:

Gamma Spectrometry Sediment samples from all three locations were analyzed for gamma emitting nuclides (Appendix C, Table C-IV.1). Nuclides detected were naturally-occurring Be-7 and K-40, as well as the fission product Cs-1 37.

Beryllium-7 was found at a two locations and ranged from 1,181 to 3,587 pCi/kg dry. Potassium-40 was found at all locations and ranged from 10,740 to 16,970 pCi/kg dry. The fission product Cs-1 37 was found at locations 16B2 and 16C4. The concentration ranged from 133 to 178 pCi/kg dry (Appendix C, Figure C-3).

The activity detected was consistent with those detected in the pre-operational years. Due to the control location, 33A2, not showing positive activity, the Cs-137 activity found at 16C4 is attributed to LGS radioactive effluent releases. The dose to a teenager's skin and whole body was conservatively calculated at 4.67E-04 mrem and 4.01 E-04 mrem, respectively. This dose represents 2.34E-03% and 6.68E-03%, of the Appendix I to 10 CFR Part 50 dose limits, respectively. No other Limerick fission or activation products were found.

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B.

Atmospheric Environment

1.

Airborne

a.

Air Particulates Continuous air particulate samples were collected from seven locations on a weekly basis. The seven locations were separated into three groups: Group I represents locations within the LGS site boundary (1 0S3, 11 S1, 13S4, and 14S1), Group II represents the locations at an intermediate distance from the LGS site (6C1 and 15D1),

and Group III represents the control location at a remote distance from LGS (22G1). The following analyses were performed:

Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Appendix C, Table C-V.1 and C-V.2).

Detectable gross beta activity was observed at all locations.

The results from the on-site locations (Group I) ranged from 7 E-3 to 31 E-3 pCi/m 3 with a mean of 15 E-3 pCi/m 3. The results from the intermediate distance location (Group II) ranged from 6 E-3 to 26 E-3 pCi/m 3 with a mean of 15 E-3 pCi/m 3. The results from the remote distance locations (Group Ill) ranged from 8 E-3 to 58 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3. Comparison of the 2014 air particulate data with previous year's data indicate no effects from the operation of LGS (Appendix C, Figure C-4). In addition, a comparison of the weekly mean values for 2013 indicate no notable differences among the three groups (Appendix C, Figure C-5).

Gamma Spectrometry Weekly samples were composited quarterly and analyzed for gamma emitting nuclides (Appendix C, Table C-V.3).

Naturally occurring Be-7 was detected in all 25 samples and is contributed to cosmic ray activity. These values ranged from 40 E-3 to 568 E-3 pCi/m 3. All other nuclides were below the required LLDs.

b.

Airborne Iodine Continuous air samples were collected from six locations (6C1, 10S3, 11S1, 13S4, 14S1, 15D1, and 22G1) and analyzed weekly for 1-131 (Appendix C, Table C-VI. 1). All results were below required LLD.

12

2.

Terrestrial

a.

Milk Samples were collected from four locations (1 8E1, 19B1, 23F1, and 25C1) biweekly April through November and monthly December through March. Samples from one additional location (36E1) were taken quarterly. The following analyses were performed:

Iodine-1 31 Milk samples from all locations were analyzed for concentrations of 1-131 (Appendix C, Table C-VII.1). One milk sample was initially positive for 1-131 at a concentration of 6.5 pCi/L. Upon further investigation recounting the sample twice showed an increase in activity, which is not congruent with 1-131 decay. Additionally, a gamma spectroscopy analysis was performed on the 1-131 sample, which determined that K-40 was the interfering isotope.

Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Appendix C, Table C-VII.2).

Naturally occurring K-40 activity was found in all samples and ranged from 968 to 1,509 pCi/L. All other nuclides were below the required LLDs.

b.

Broad Leaf Vegetation Five types of broad leaf vegetation samples were collected from three locations (11 S3, 13S3, and 31 GI) monthly from June through October. The following analysis was performed:

Strontium Each broad leaf vegetation sample was analyzed for concentrations of Sr-89 and Sr-90 (Appendix C, Table C-VIII.I).

Ten of 45 samples were positive for Sr-90. The concentration ranged from 2.3 to 6.8 pCi/kg wet. The largest source of Sr-90 in the environment (-99%) is from weapons testing fallout. Approximately 16.8 million curies of strontium-90 were produced and globally dispersed in atmospheric nuclear weapons testing until 1980. As a result 13

of the Chernobyl accident, approximately 216,000 curies of Sr-90 were released into the atmosphere. With a 28 year half-life, Sr-90 still remains in the environment at nominal levels. The total annual release of strontium-90 into the atmosphere from all 103 commercial nuclear power plants operating in the United States is typically 1/1000th of a curie.

(NUREG/CR-2907 Vol.12). At an individual nuclear power plant, the amount of Sr-90 is so low that it is usually at or below the minimum detectable activity of sensitive detection equipment. Limerick did not report any Sr-90 released in the Annual Radioactive Effluent Release Report, as all analyses for Sr-90 performed were below the required LLD.

Gamma Spectrometry Each broad leaf vegetation sample was analyzed for concentrations of gamma emitting nuclides (Appendix C, Table C-VIII.1).

Cosmogenic Be-7 was found in 16 of 45 samples and ranged from 192 to 1,335 pCi/kg wet. Naturally occurring K-40 was found in all samples and ranged from 2,074 to 10,280 pCi/kg wet. All other nuclides were below the required LLDs.

C.

Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Panasonic 814 (CaSO4) thermoluminescent dosimeters. Forty dosimeter locations were established around the site. Results of dosimeter measurements are listed in Appendix C, Tables C-IX.1 and C-IX.2, Figure C-6.

Dosimeter measurements were reported in mR/standard month. Most dosimeter measurements were below 10 mR/standard month, with a range of 2.1 to 10.9 mR/month. A comparison of the Site Boundary and Intermediate Distance data to the Control Location (5H1) data indicate that the ambient gamma radiation levels from the Control Location were consistently higher than all other locations, except 13S2. Location 13S2 historically shows higher ambient gamma radiation, which is due to the rock substrate. The area that this dosimeter is located in has been determined to emanate radon prodigy.

D.

10 CFR 20.2002 Permit Storage Area The results of the surface water aquatic monitoring program from Location 24S1 were used to determine if radioactivity from the permit storage area had made it to the Schuylkill River. The data obtained from the gamma analysis program did not detect any migration of radioactivity from the 14

permit storage area.

E.

Independent Spent Fuel Storage Installation The result of the ambient gamma radiation level at dosimeter location 36S2 was used to determine the direct radiation exposure to the nearest residence from the ISFSI pad. The data, after subtracting background, shows the net direct radiation exposure to the nearest residence was 0.0 mrem for the year.

F.

Land Use Survey A Land Use Survey conducted in July and October 2014 around Limerick Generating Station (LGS) was performed by Normandeau Associates, Inc.

for Exelon Nuclear to comply with Bases 3.3.2 of the Limerick's Offsite Dose Calculation Manual. The purpose of the survey was to document the nearest resident, milk producing animal and garden of greater than 500 ft2 in each of the sixteen 22 1/2 degree sectors out to five miles around the site. The distance and direction of all locations from the LGS reactor buildings were positioned using Global Positioning System (GPS) technology. There were no changes required to the LGS REMP, as a result of this survey. The results of this survey are summarized below.

Distance in feet from the LGS Reactor Buildings (Out to 26,400 feet)

Sector Residence Garden Milk Farm Meat Animal Feet Feet Feet Feet 1

N 3,109 3,333 24,775 24,775 2

NNE 2,706 9,611 13,015 3

NE 3,469 3,494 16,044 4

ENE 3,231 14,208 20,553 5

E 2,864 4,116 6

ESE 3,434 4,498 12,385 7

SE 5,108 6,568 10,927 8

SSE 5,403 6,912 9

S 4,347 6,103 22,114 12,210 10 SSW 5,063 5,321 10,390 10,390 11 SW 3,251 4,558 12 WSW 3,799 4,507 14,177 14,177 13 W

3,627 4,321 14,884 14 WNW 3,932 3,932 15 NW 3,619 8,200 16 NNW 5,050 5,586 G.

Errata Data The Dosimetry data was documented as a gross value in the 2013 ARERR. Re-evaluation of the data was performed, subtracting out extraneous dose. Extraneous dose is the dose accumulated on a dosimeter prior to and after field deployment from radiation other than that at the field monitoring location. The extraneous dose can include 15

natural terrestrial background radiation, cosmic sources, elevated dose from transport at high altitudes, any manmade sources potentially encountered in transit or at the facility, such as shipments of medical or other radioisotopes or facility sources. The extraneous dose is subtracted from the field dosimeter reading in order to determine the field dose. The subtraction of extraneous dose (also referred to as transit dose) is recommended by ANSI N545-1975, which is supported by the Regulatory Guide 4.13 Revision 1 (July 1977). This change impacts three sections of the 2013 report. The revised data can be found in Appendix F.

H.

Summary of Results - Inter-laboratory Comparison Program The primary and secondary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation, and water matrices for various analytes. (Appendix E) The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:

1.

Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TBE's result and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal QC requirements, which are based on the DOE MAPEP criteria.

2.

ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA, National Environmental Laboratory Accreditation Conference (NELAC), state specific Performance Testing (PT) program requirements or ERA's SOP for the Generation of Performance Acceptance Limits, as applicable.

The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.

3.

DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values.

The MAPEP defines three levels of performance: Acceptable (flag = "A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable 16

when a mean result for the specified analyte is +/- 20% of the reference value. Performance is acceptable with warning when a mean result falls in the range from +/- 20% to +/- 30% of the reference value. If the bias is greater than 30%, the results are deemed not acceptable.

In reviewing our environmental inter-laboratory crosscheck programs, we identified 1) duplication of efforts on some matrices and isotopes and 2) that we are performing crosscheck samples on some matrices and isotopes that we do not perform for clients. Since the DOE MAPEP is designed to evaluate the ability of analytical facilities to correctly analyze for radiological constituents representative of those at DOE sites, the needed changes were made to the MAPEP program. Therefore, the following isotopes were removed from the MAPEP program:

Soil - gamma - will be provided by Analytics twice per year, starting in 2015. For 2014, one soil gamma is provided by MAPEP, the 2nd soil gamma is provided by Analytics.

AP - gamma - is currently provided by Analytics.

Water - gamma, H-3, Sr-90, uranium, gross alpha and gross beta currently provided by ERA.

MAPEP evaluates non-reported (NR) analyses as failed if they were reported in the previous series.

For the TBE laboratory, 163 out of 169 analyses performed met the specified acceptance criteria. Six analyses (Ni-63, K-40 and 1-131 in water, and two Sr-90s and one Gross Alpha in AP samples) did not meet the specified acceptance criteria for the following reasons:

1.

Teledyne Brown Engineering's MAPEP March 2014 Ni-63 in water result of 32.7 +/- 1.69 Bq/L was overlooked when reporting the data but would have passed the acceptance range of 23.9 - 44.2 Bq/L.

NCR 14-04

2.

Teledyne Brown Engineering's MAPEP March 2014 K-40 in water result of 1.63 +/- 2.49 Bq/L was overlooked when reporting the data but would have passed the false positive test. NCR 14-04

3.

Teledyne Brown Engineering's ERA November 2014 1-131 in water result of 15.8 pCi/L was lower than the known value of 20.3 pCi/L, falling below the lower acceptance limit of 16.8. The result was evaluated as failed with a found to known ratio of 0.778. No cause could be found for the slightly low result. All previous ERA 1-131 evaluations since 2004 have been acceptable. NCR 14-08

4.

Teledyne Brown Engineering's MAPEP March 2014 Sr-90 in AP result of 0.822 Bq/sample was lower than the known value of 1.18 Bq/sample, falling below the lower acceptance limit of 0.83 Bq/sample. The rerun result was still low, but fell within the lower 17

acceptance range of 0.836 Bq/sample. No cause could be found for the slightly low results. NCR 14-04

5.

Teledyne Brown Engineering's MAPEP September 2014 Sr-90 in AP result of 0.310 Bq/sample was lower than the known value of 0.703 Bq/sample. The gravimetric yield of 117% was very high (we normally see yields of 60% to 70%) and could account for the low activity. NCR 14-09

6.

Teledyne Brown Engineering's MAPEP September 2014 Gr-Alpha in AP result of 0.153 Bq/sample was lower than the known value of 0.53 Bq/sample. The AP sample was counted on the wrong side.

The AP was flipped over and recounted with acceptable results.

NCR 14-09 For the EIML laboratory, 85 of 90 analyses met the specified acceptance criteria. Five analyses (Water - Pu-238, Pu-239, Fe-55; AP - Co-57; Soil

- Csi 34) did not meet the specified acceptance criteria for the following reasons:

1. Environmental Inc., Midwest Laboratory's MAPEP February 2014 water Pu-238 result of 1.28 Bq/L was higher than the known value of 0.83 Bq/L, exceeding the upper control limit of 1.08 Bq/L. The high bias on the plutonium was traced to contamination from a newly purchased standard. The result of the reanalysis with the new tracer was 0.68, which fell within the acceptance criteria.

2. Environmental Inc., Midwest Laboratory's MAPEP February 2014 water Pu-239/240 result of 0.91 Bq/L was higher than the known value of 0.68 Bq/L, exceeding the upper control limit of 0.88 Bq/L.

The high bias on the plutonium was traced to contamination from a newly purchased standard. The result of reanalysis with the new tracer was 0.66 Bq/L, which fell within the acceptance criteria.

3. Environmental Inc., Midwest Laboratory's MAPEP February 2014 AP Co-57 result of 1.60 +/- 0.05 Bq/total sample failed the false positive test. Interference from the Eu-1 52 resulted in the misidentification of Co-57.

4. Environmental Inc., Midwest Laboratory's MAPEP February 2014 soil Cs-1 34 result of 6.10 +/- 1.80 Bq/kg failed the false positive test.

Long sample counting time lead to interference from naturally occurring Bi-214 in the sample matrix with a close spectral energy.

5. Environmental Inc., Midwest Laboratory's MAPEP August 2014 water Fe-55 result of 55.10 +/- 14.80 Bq/L was higher than the known value of 31.50 Bq/L, exceeding the upper control limit of 18

41.00 Bq/L. The result of the reanalysis of Fe-55 was 32.63 +

16.30 Bq/L, which fell within the acceptance criteria.

The Inter-Laboratory Comparison Program provides evidence of "in control" counting systems and methods, and that the laboratories are producing accurate and reliable data.

V.

References A.

Environmental Report Operating License Stage, Limerick Generating Station, Units 1 and 2, Volumes 1-5 Philadelphia Electric Company B.

NUREG-1302 Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors C.

Branch Technical Position Paper, Regulatory Guide 4.8, Revision 1, November 1979 D.

Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2, 1 January 1982 through 21 December 1984, Teledyne Isotopes and Radiation Management Corporation 19

Intentionally Left Blank

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

Intentionally left blank

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2014 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2014 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS SURFACE WATER (PCI/LITER)

H-3 8

200

<LLD

<LLD 0

GAMMA MN-54 CO-58 FE-59 CO-60 24 15

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD 15

<LLD

<LLD 0

0 0

ZN-65 NB-95 ZR-95 30

<LLD

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2014 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2014 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS SURFACE WATER (PCI/LITER) 1-131 I i CS-1 34 CS-137 BA-140 LA-140 15

<LLD 15

<LLD 18

<LLD 60

<LLD 15

<LLD 4

3.8 (27/36)

(2.3/6.7) 200

<LLD 1

<LLD

<LLD 0

0 0

DRINKING WATER (PCI/LITER)

GR-B H-3 1-131 48 16 48 3.6 (9/12)

(2.1/5.0) 4.1 (10/12)

(2.7/5.3) 15F4 INDICATOR 0

PHILADELPHIA SUBURBAN WATER COMPANY 8.62 MILES SE OF SITE

<LLD

<LLD 0

0

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2014 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2014 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS DRINKING WATER (PCI/LITER)

GAMMA MN-54 CO-58 FE-59 CO-60 48 15

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD

<LLD 0

0 0

0 ZN-65 NB-95 ZR-95 CS-134 15

<LLD

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2014 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2014 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS DRINKING WATER (PCI/LITER)

CS-137 BA-140 LA-140 GAMMA K-40 MN-54 CO-58 18

<LLD 60

<LLD 15

<LLD

<LLD 0

0 0

BOTTOM FEEDER (PCI/KG WET) 4 NA 3280 (2/2)

(3169/3390) 3685 (2/2)

(3402/3967) 3685 (2/2)

(3402/3967) 29CI CONTROL POTTSTOWN VICINITY UPSTREAM OF INTAKE 130

<LLD 130

<LLD 260

<LLD

<LLD 0

0 0

FE-59 0

0 CO-60 130

<LLD

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2014 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2014 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS BOTTOM FEEDER (PCI/KG WET)

ZN-65 1-131 260

<LLD NA

<LLD 130

<LLD 150

<LLD

<LLD 0

0 0

0 PREDATOR (PCI/KG WET)

CS-134 CS-1 37 GAMMA K-40 MN-54 CO-58 4

NA 4908 (2/2)

(4113/5702) 3479 (2/2)

(3123/3835) 4908 (2/2)

(4113/5702) 16C5 INDICATOR VINCENT POOL DOWNSTREAM OF DISCHARGE 130

<LLD 130

<LLD

<LLD 0

0 0

0 FE-59 260

<LLD

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2014 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2014 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS PREDATOR (PCI/KG WET)

CO-60 ZN-65 1-131 130

<LLD 260

<LLD NA

<LLD 130

<LLD 150

<LLD

<LLD 0

0 0

CS-134 CS-137 GAMMA BE-7 0

0 SEDIMENT (PCI/KG DRY) 6 NA 2384 (2/4)

(1181/3587)

NA 15540 (4/4)

(14160/16970)

<LLD 3587 (1/2) 16C4 INDICATOR VINCENT DAM 2.18 MILES SSE OF SITE 16C4 INDICATOR VINCENT DAM 2.18 MILES SSE OF SITE K-40 12425 (2/2)

(10740/14110) 15565 (2/2)

(14160/16970) 0 0

0 MN-54 NA

<LLD

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2014 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2014 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS SEDIMENT (PCI/KG DRY)

CO-58 CO-60

-- l 1-131 CS-134 CS-137 NA

<LLD NA

<LLD 150

<LLD 180 158 (3/4)

(133/178) 10 15 (269/272)

(6/31)

NA 63 (21/21)

(40/88)

<LLD

<LLD 0

0 0

0 AIR PARTICULATE (E-3 PCI/CU.METER)

GR-B 311

<LLD 17 (37/39)

(8/58) 195 (4/4)

(55/568) 178 (1/2) 17 (37/39)

(8/58) 195 (4/4)

(55/568) 16B2 INDICATOR LINFIELD BRIDGE 1.35 MILES SSE OF SITE 22G1 CONTROL MANOR SUBSTATION 17.73 MILES SW OF SITE 22G1 CONTROL MANOR SUBSTATION 17.73 MILES SW OF SITE GAMMA BE-7 MN-54 25 0

0 NA

<LLD

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2014 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2014 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS AIR PARTICULATE (E-3 PCI/CU.METER) 00 CO-58 CO-60 CS-134 CS-137 GAMMA 1-131 NA

<LLD NA

<LLD 50

<LLD 60

<LLD

<LLD 0

0 0

0 AIR IODINE (E-3 PCI/CU.METER) 311 70

<LLD

<LLD 0

0 MILK (PCI/LITER) 1-131 92 92 1

1.4 (1/66)

NA 1264 (66/66)

(1077/1509)

<LLD 1259 (26/26)

(968/1407) 1.4 (1/22) 1292 (22/22)

(1118/1407) 25C1 INDICATOR 2.69 MILES WSW OF SITE 23F1 CONTROL 5.02 MILES SW OF SITE GAMMA K-40 0

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2014 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2014 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS MILK (PCI/LITER)

'0 CS-134 CS-137 BA-140 LA-140 SR-89 SR-90 GAMMA BE-7 15

<LLD 18

<LLD 60

<LLD 15

<LLD 25

<LLD

<LLD 0

0 0

0 VEGETATION (PCl/KG WET) 45 45 45 5

4.4 (6/30)

(2.3/6.8)

NA 349 (8/30)

(277/489) 5.1 (4/15)

(4.4/5.8) 463 (8/15)

(192/1335) 5.1 (4/15)

(4.4/5.8) 463 (8/15)

(192/1335) 31G1 CONTROL 31G1 CONTROL 0

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2014 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2014 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS VEGETATION (PCI/KG WET)

K-40 NA 5054 (30/30)

(2074/9455) 6383 (15/15)

(2880/10280) 6383 (15/15)

(2880/10280) 31G1 CONTROL 0

MN-54 CO-58 CO-60 NA

<LLD NA

<LLD 60

<LLD 80

<LLD

<LLD 0

0 0

0 1-131 0

CS-134 CS-137

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2014 NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 2014 LOCATION OF FACILITY: MONTGOMERY, PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS VEGETATION (PCI/KG WET)

RA-226 TH-228 TH-232 NA 1310 (8/30)

(457/2107)

NA 43 (1/30)

NA

<LLD NA 6.0 (156/156)

(2.1/10.9) 535 (2/15)

(496/575)

<LLD 1310 (8/15)

(457/2107) 43 (1/15) 13S3 INDICATOR VINCENT DAM 0.24 MILES SE OF SITE 13S3 INDICATOR VINCENT DAM 0.24 MILES SE OF SITE 0

0 0

0

<LLD DIRECT RADIATION TLD-QUARTERLY (MILLI-ROENTGEN/STD.MO.)

160 7.8 (4/4)

(6.3/9.3) 9.3 (4/4)

(6.9/10.9) 13S2 INDICATOR 500 KV SUBSTATION 0.41 MILES SE

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

Intentionally left blank

APPENDIX B LOCATION DESIGNATION, DISTANCE &

DIRECTION, AND SAMPLE COLLECTION &

ANALYTICAL METHODS

Intentionally left blank

TABLE B-1:

XXYZ -

Location Designation and Identification System for the Limerick Generating Station General code for identification of locations, where:

xx Y

Angular Sector of Sampling Location. The compass is divided into 36 sectors of 10 degrees each with center at Limerick's Units 1 and 2 off-gas vents. Sector 36 is centered due North, and others are numbered in a clockwise direction.

Radial Zone of Sampling Location (in this report, the radial distance from the Limerick vent for all regional stations).

S A

B C

D on-site location 0-5,280 feet off-site 5,280-10,560 feet off-site 10,560-15,840 feet off-site 15,840-21,120 feet off-site E

F G

H 21,120-26,400 feet off-site 26,400-52,800 feet off-site 52,800-105,600 feet off-site 105,600-528,000 feet off-site Z

Station's Numerical Designation within sector and zone, using 1, 2, 3... in each sector and zone.

B-I

TABLE B-2:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2014 Location Location Description Distance & Direction From Site A.

Surface Water 1381 24S1 Vincent Dam Limerick Intake (control) 9,225 feet SE 1,058 feet SW B.

Drinking (Potable) Water 151F4 15F7 16C2 28F3 AQUA Water Company Phoenixville Water Works Citizens Home Water Company Pottstown Water Authority (control)

C.

Milk - bi-weekly / monthly 10F4 18E1 19B1 23F1 Control 25C1 D.

Milk - quarterl 36E1 Control E.

Air Particulates / Air Iodine 45,514 feet SE 33,400 feet SSE 14,034 feet SSE 30,811 feet WNW 34,848 feet ESE 22,229 feet S 10,317 feet SSW 26,505 feet SW 14,224 feet WSW 24,816 feet N 10S3 11S1 11S2 13C1 13S4 14S1 15D1 22G1 6C1 Keen Road LGS Information Center LGS Information Center (quality control)

King Road Longview Road, near 500 kv Yard Longview Road Spring City Substation Manor Substation (control)

Limerick Airport 2,648 feet E 2,017 feet ESE 2,017 feet ESE 14,980 feet SE 1,186 feet SE 3,319 feet SSE 16,877 feet SE 93,619 feet SW 11,305 feet NE F.

Fish 16C5 29C1 Vincent Pool Pottstown Vicinity (control)

Downstream of Discharge Upstream of Intake G.

Sediment 1682 16C4 33A2 Linfield Bridge Vincent Dam Upstream of Intake (control) 7,128 feet SSE 11,510 feet SSE 4,435 feet NNW H.

Broad Leaf Vegetation 11S3 13S3 31G1 LGS Information Center LGS 500 KV Yard Prout's Jollyview Farm (control) 1,848 feet ESE 1,267 feet SE 71,808 feet NW B-2

TABLE B-2:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2014 Location Location Description Distance & Direction From Site I. Environmental Dosimetry - DLR Site Boundary 36S2 3S1 5S1 7S1 10S3 11SI 13S2 14S1 18S2 21S2 23S2 25S2 26S3 29S1 31S1 34S2 Evergreen & Sanatoga Road Sanatoga Road Possum Hollow Road LGS Training Center Keen Road LGS Information Center 500 KV Substation Longview Road Rail Line along Longview Road Near Intake Building Transmission Tower Sector Site Boundary Met. Tower #2 Sector Site Boundary Sector Site Boundary Met. Tower #1 Intermediate Distance 36D1 2E1 4E1 7E1 10E1 10F3 13E1 16F1 19D1 20F1 24D1 25D1 28D2 29E1 31D2 34E1 Siren Tower No. 147 Laughing Waters GSC Neiffer Road Pheasant Road Royersford Road Trappe Substation Vaughn Substation Pikeland Substation Snowden Substation Sheeder Substation Porters Mill Substation Hoffecker & Keim Streets W. Cedarville Road Prince Street Poplar Substation Vamell Road 3,183 feet N 2,301 feet NNE 2,350 feet NE 3,099 feet ENE 2,648 feet E 2,017 feet ESE 2,149 feet SE 3,319 feet SSE 1,390 feet S 977 feet SSW 2,793 feet SW 2,445 feet WSW 2,088 feet W 2,886 feet WNW 1,395 feet NW 3,071 feet NNW 18,527 feet N 25,112 feet NNE 25,221 feet NE 22,489 feet ENE 20,826 feet E 29,442 feet ESE 22,772 feet SE 26,608 feet SSE 18,439 feet S 27,648 feet SSW 20,972 feet SW 21,044 feet WSW 20,231 feet W 26,110 feet WNW 20,446 feet NW 24,243 feet NNW 130,742 feet NE 11,305 feet NE 11,377 feet E 14,980 feet SE 16,877 feet SE 8,462 feet S 16,157 feet SSW 15,853 feet WNW Control and Special Interest 5H1 6C1 9C1 13C1 1501 17B1 20D1 31D1 Birch Substation (control)

Limerick Airport Reed Road King Road Spring City Substation Linfield Substation Ellis Woods Road Lincoln Substation B-3

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2014 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Surface Water Gamma Spectroscopy Monthly composite from RMC-ER5 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis a continuous water radiological analysis (Limerick Generating compositor Station)

Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Surface Water Tritium Quarterly composite RMC-ER5 Collection of water samples for 500 ml TBE, TBE-2011 Tritium analysis in drinking water by liquid from a continuous water radiological analysis (Limerick Generating scintillation compositor Station)

Env. Inc., T-02 Determination of tritium in water (direct method)

Drinking Water Gross Beta Monthly composite from RMC-ER5 Collection of water samples for 2 gallon TBE, TBE-2008 Gross Alpha and/or gross beta activity in a continuous water radiological analysis (Limerick Generating various matrices compositor Station)

Env. Inc., W(DS)-01 Determination of gross alpha and/or gross beta in water (dissolved solids or total residue)

Env. Inc., W(SS)-02 Determination of gross alpha and/or gross beta in water (suspended solids)

Drinking Water 1-131 Monthly composite from RMC-ER10 Collection of water samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices a continuous water radiological analysis (Limerick Generating compositor Station)

Env. Inc., 1-131-01 Determination of 1-131 in water by an ion exchange Drinking Water Gamma Spectroscopy Monthly composite from RMC-ER5 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis a continuous water radiological analysis (Limerick Generating compositor Station)

Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Drinking Water Tritium Quarterly composite RMC-ER5 Collection of water samples for 500 ml TBE, TBE-2011 Tritium analysis in drinking water by liquid from a continuous water radiological analysis (Limerick Generating scintillation compositor Station)

Env. Inc., T-02 Determination of tritium in water (direct method)

Fish Gamma Spectroscopy Semi-annual samples RMC-ER6 Collection of fish samples for 1000 grams (wet)

TBE-2007 Gamma emitting radioisotope analysis collected via radiological analysis (Limerick Generating electroshocking or other Station)

Env. Inc., GS-01 Determination of gamma emitters by techniques gamma spectroscopy Sediment Gamma Spectroscopy Semi-annual grab RMC-ER7 Collection of sediment samples for 500 grams (dry)

TBE, TBE-2007 Gamma emitting radioisotope analysis samples radiological analysis (Limerick Generating Station)

Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Air Particulates Gross Beta One-week composite of RMC-ER8 Collection of air particulate and air I filter (approximately TBE, TBE-2008 Gross Alpha and/or gross beta activity in continuous air sampling iodine samples for radiological analysis 280 cubic meters various matrices through glass fiber filter (Limerick Generating Station) weekly) paper Env. Inc., AP-02 Determination of gross alpha and/or gross beta in air particulate filters B-4

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2014 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Air Particulates Gamma Spectroscopy Quarterly composite of TBE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting radioisotope analysis each station (approximately 3600 Env. Inc., AP-03 Procedure for compositing air cubic meters)

Env. Inc., GS-01 Determination of gamma emitters by particulate filters for gamma spectroscopic gamma spectroscopy analysis Air Iodine Gamma Spectroscopy One-week composite of RMC-ER8 Collection of air particulate and air 1 filter (approximately TBE, TBE-2007 Gamma emitting radioisotope analysis continuous air sampling iodine samples for radiological analysis 280 cubic meters through charcoal filter (Limerick Generating Station) weekly)

Env. Inc., 1-131-02 Determination of 1-131 in charcoal canisters by gamma spectroscopy (batch method)

Milk 1-131 Bi-weekly grab sample RMC-ER10 Collection of milk samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices when cows are on radiological analysis (Limerick Generating pasture. Monthly all Station)

Env. Inc., 1-131-01 Determination of 1-131 in milk by anion other times exchange Milk Gamma Spectroscopy Bi-weekly grab sample RMC-ER10 Collection of milk samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis when cows are on radiological analysis (Limerick Generating pasture. Monthly all Station)

Env. Inc., GS-01 Determination of gamma emitters by other times gamma spectroscopy DLR Thermoluminescent Quarterly DLRs RMC-ER9 Collection of dosimetry samples for 2 dosimeters Mirion Technologies Dosimetry comprised of two radiological analysis (Limerick Generating dosimeter elements Station)

I B-5

Figure B-1 Environmental Sampling Locations Within 5,280 Feet of the Limerick Generating Station, 2014 B-6

Figure B-2 Environmental Sampling Locations Between 5,280 and 26,400 Feet from the Limerick Generating Station, 2014 B-7

N NNW 0NEH

~N-E BEEN 3101 283imedrik 0 9GI 422 I0F4 220 100 SE

.5 1

mm==mmnn *=

Miles Figure B-3 Environmental Sampling Locations Greater than 26,400 Feet from the Limerick Generating Station, 2014 B-8

APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY

Intentionally left blank

Table C-1.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION 13B1 24S1 PERIOD 12/31/13 - 04/01/14

< 191

< 190 04/01/14 - 07/01/14

< 169

< 171 07/01/14 - 09/29/14

< 175

< 176 09/29/14 - 12/29/14

< 185

< 184 MEAN C-I

Table C-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD 13B1 12/30/13 - 01/27/14

<4

<5

< 10

<4

< 8

< 5

<8

< 12

<4

< 5

<26

< 9 01/27/14 - 03/04/14

< 4

< 5

< 11

< 6

< 10

< 5

< 9

< 10

< 5

< 26

< 7 03/04/14 - 04/01/14

< 7

< 6

< 14

< 5

< 15

< 6

< 11

< 12

< 6

< 7

< 27

< 11 04/01/14 - 04/29/14

< 4

< 10

< 5

< 10

< 4

< 9

< 13

< 4

< 5

< 25

< 10 04/29/14 - 06/03/14

< 5

< 13

< 5

< 13

< 6

< 11

< 6

< 29

< 10 06/03/14 - 07/01/14

< 5

< 6

< 12

< 6

< 11

< 5

< 9

< 11

< 5

< 6

< 22

< 9 07/01/14 - 07/29/14

< 6

, 12

< 5

< 11

< 5

< 9

< 5

< 24

< 6 07/29/14 - 09/02/14

< 6

< 11

< 5

< 11

< 5

< 10

< 13

< 5

< 6

< 31

< 9 09/02/14 - 09/29/14

< 6

< 12

< 6

< 13

< 6

< 12

< 13

< 6

< 5

< 40

< 11 09/29/14 - 10/28/14

< 5

< 10

< 7

< 11

< 5

< 8

< 9

< 5

< 25

< 8 10/28/14 - 12/02/14

< 5

< 7

< 11

< 6

< 13

< 5

< 10

< 11

< 6

< 32

< 8 12/02/14 - 12/29/14

< 5

< 11

< 8

< 9

< 8

< 11

< 12

< 6

< 5

< 29

< 11 MEAN 24S1 12/30/13 - 01/27/14

< 6

< 5

< 10

< 7

< 11

<6

< 8

< 15

< 6

< 7

< 33

< 12 01/27/14 - 03/04/14

< 5

< 6

< 14

< 6

< 15

< 8

< 12

< 13

< 5

< 6

< 30

< 11 03/04/14 - 04/01/14

< 4

< 6

< 10

< 6

< 10

< 4

< 11

< 10

< 4

< 6

< 27

< 9 04/01/14 - 04/29114

< 5

< 12

< 5

< 11

< 6

< 10

< 14

< 5

< 6

< 32

< 8 04/29/14 - 06/03/14

< 6

< 14

< 7

< 11

< 6

< 10

< 13

< 5

< 6

< 32

< 10 06/03/14 - 07/01/14

< 4

< 7

< 4

< 8

< 5

< 7

< 4

< 21

< 7 07/01/14 - 07/29/14

< 4

< 6

< 4

< 6

< 4

< 6

< 4

< 16

< 4 07/29/14 - 09/02/14

< 6

< 16

< 5

< 11

< 7

< 12

< 13

< 6

< 25

< 11 09/02/14 - 09/29/14

< 7

< 16

< 6

< 13

< 6

< 13

< 15

< 5

< 6

< 35

< 12 09/29/14 - 10/28/14

< 6

< 5

< 15

< 6

< 15

< 7

< 12

< 7

< 5

< 31

< 6 10/28/14 - 12/02/14

< 6

< 7

< 14

< 7

< 15

< 8

< 13

< 14

< 7

< 8

< 32

< 8 12/02/14 - 12/29/14

< 8

< 9

< 6

< 14

< 6

< 10

< 12

< 6

< 7

< 35

< 12 MEAN

Table C-I1.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 12/30/13 -01/27/14 01/27/14 - 03/04/14 03/04/14 - 04/01/14 04/01/14 - 04/29/14 04/29/14 - 06103/14 06/03/14 - 07/01/14 07/01/14 - 07/29/14 07/29/14 - 09/02/14 09/02/14 - 09/29/14 09/29/14 - 10/28/14 10/28/14 - 12/02/14 12/02/14 - 12/29/14 15F4 15F7 16C2 28F3 2.7 +/-

4.7 +/-

4.1 +/-

< 2.2 4.0 +/-

3.4 +/-

3.0 +/-

4.8 +/-

5.3 +/-

4.3 +/-

5.1 +/-

< 2.2 1.5 1.8 1.6 1.4 1.5 1.7 2.0 2.0 1.9 1.8 2.3 5.4 2.6 2.4 3.3 2.7 3.8 6.7 5.3 3.2 3.7

< 2.1

+/- 1.4

+/- 1.7

+/- 1.4

+/- 1.5

+/- 1.3

+/- 1.4

+/- 1.8

+/- 2.3

+/- 2.0

+/- 1.8

+/- 1.7 3.0 +/- 1.6 3.5 +/- 1.6

< 2.1

< 2.3 2.4 +/- 1.3 3.1 +/- 1.5

< 2.5 4.3 +/- 1.8

< 2.7

< 2.7 3.7 +/- 1.7

< 2.3 3.3 +/- 1.3 2.1 +/- 1.4 3.9 +/- 1.7 2.6 +/- 1.4

< 2.2 3.1 +/- 1.3 4.0 +/- 1.5 2.7 +/- 1.6 4.4 +/- 1.8 5.0 +/- 1.9

< 2.6 4.8 +/- 1.7

< 2.1 3.6 +/- 2.0 MEAN 4.1 +/- 1.8 3.8 +/- 2.9 Table C-II.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 15F4 15F7 16C2 28F3 12131/13 - 04/01/14 04/01/14 - 07/01/14 07/01/14 - 09/29/14 09/29/14 - 12/29/14 I vo

< 173

< 181

< 184

< 171

< 178

< 184

< 170

< 181

< 185

< zuu

< 172

< 178

< 181 MEAN Table C-II.3 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN'UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 12/30/13 - 01/27/14 01/27/14 - 03/04/14 03/04/14 - 04/01/14 04/01/14 - 04/29/14 04/29/14 - 06/03/14 06/03/14 - 07/01/14 07/01/14 - 07/29/14 07/29/14 - 09/02/14 09/02/14 - 09/29/14 09/29/14 - 10/28/14 10/28/14 - 12/02/14 12/02/14 - 12/29/14 15F4 15F7 16C2 28F3

< 0.8

< 0.9

< 0.6

< 0.3

< 0.7

< 0.6

< 0.5

< 0.6

< 0.8

< 0.5

<0.7

< 0.8

< 0.9

< 0.6

< 0.3

< 0.6

< 0.4

< 0.5

< 0.6

< 0.8

< 0.6

< 0.5

< U.Y

< 0.8

< 0.6

< 0.3

< 0.6

< 0.5

< 0.6

< 0.7

< 0.8

< 0.5

< 0.8

< U.7

< 0.7

< 0.3

< 0.7

< 0.6

< 0.7

< 0.8

< 0.6

< 0.7 MEAN THE MEAN AND TWO STANDARD DEVIATION AR CALCULATED USING THE POSITIVE VALUES C-3

Table C-II.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- SIGMA SITE COLLECTION PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 151-4 12130113 - 01/271/14 01/27/14 - 03/04/14 03/04/14 - 04/01/14 04/01/14 - 04/29/14 04/29/14 - 06/03/14 06/03/14 - 07/01/14 07/01/14 - 07/29/14 07/29/14 - 09/02/14 09/02/14 - 09/29/14 09/29/14 - 10/28/14 10/28/14 - 12/02/14 12/02/14 - 12/29/14 MEAN 15F7 12/30/13 - 01/27/14 01/27/14 - 03/04/14 03/04/14 - 04/01/14 04/01/14 - 04/29/14 04/29/14 - 06/03/14 06/03/14 - 07/01/14 07101/14 - 07/29/14 07/29/14 - 09/02/14 09/02/14 - 09/29/14 09/29/14 - 10/28/14 10/28/14 - 12/02/14 12/02/14 - 12/29/14

<5

< 5

<6

<7

<4

<5

<6

<3

<4

<6

<4

<6

<5

<3

<5

<4

<7

<. t

<6

<4

<5

<6

<3

<5

<7

<3

<5

<6

<4

<5

<6

<5

<6

<3

<4

<5

<4

<9

<11

10

10

<11

< 12

<5

<8

12

14

<7

<9

<11

<8

< 10

14

<9

12

< 13

<7

10

12

<8

< 18

<6

<4

<5

<7

<4

<5

<7

<3

<5

<4

<7

<4

<3

<4

<5

<4

<7 11

<9

<11

< 14

<8

<7

< 10

<12

<9

< 10

< 13

<11

<7

< 11

< 10

<11

<6

<9

< 12

<7

< 13

<6

<5

<6

<8

<3

<4

<6

<7

<4

<6

<4

<7

<5

<6

<3

<5

<4

<8

<11

<8

<9

<10

< 14

<6

<8

< 11

<11

<7

<10

<8

<7

< 11

<9

<6

<10

<11

<6

< 11

<5

<4

<5

<6

<7

<4

<5

<8

<3

<4

<6

<4

<3

<6

<5

<6

<5

<3

<5

<4

<7

<6

<5

<6

<8

<4

<7

<6

<3

<5

<6

<5

<6

<5

<6

<3

<5

<6

<4

<7

26

21

< 30

< 32

< 37

< 17

23

< 32

36

< 17

< 26

32

< 21

20

< 33

< 25

29

29

< 17

28

31

21

< 34 IU

<8

<7

< 10

<9

<8

<4

<8

< 10

10

<5

<8

< 12

<8

<6

<9

<8

<9

<8

<4

<9

<5

<8

< 13 MEAN

Table C-II.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- SIGMA SITE COLLECTION PERIOD 16C2 12/30/13 - 01/27/14 01/27/14 - 03/04/14 03/04/14 - 04/01/14 04/01/14 - 04/29/14 04/29/14 - 06/03/14 06/03/14 - 07/01/14 07/01/14 - 07/29/14 07/29/14 - 09/02/14 09/02/14 - 09/29/14 09/29/14 - 10/28/14 10128/14 - 12/02/14 12/02/14 - 12/29/14 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-1 37 Ba-140 La-140 MEAN 28F3 12/30/13 01/27/14 03/04/14 04/01/14 04/29/14 06/03/14 07/01/14 07/29/14 09/02/14 09/29/14 10/28/14 12/02/14

<5

<6

<5

<6

<4

<6

<5

<6

<5

<4

<6

<5

<6

<7

<5

<3

<4

<7

<5

<4

<5

<8

<5

<7

<6

<5

<7

<6

<4

<6

<7

<6

<5

< 12

<11

< 10

<10

10

<11

14

<15

<13

<12

<9

16

13

<11

13

13

12

10

<7

<10

<17

14

10

<8

<5

<6

<5

<6

<5

<6

<7

<8

<7

<4

<9

<7

<6

<7

<5

<4

<5

<9

<7

<4

<5

<11

<9

< 13

14

< 14

<8

10

12

<11

<9

<9 11

< 13

<15

< 10

<8

< 16

14

< 10

<9

<6

<5

<6

<4

<5

<6

<7

<6

<5

<6

<5

<6

<7

<5

<4

<5

<6

<5

<9

< 10

<9

< 10

<8

< 11

<9

<13

<9

<11

<10

<9

12

< 12

<9

<6

<7

<12

13

<10

<7

<5

<6

<5

<4

<5

<6

<5

<4

<5

<6

<5

<6

<5

<4

<7

<5

<6

<5

<7

<5

<6

<7

<5

<4

<8

<7

<6

<5

< 29

< 35

< 23

< 25

25

< 24

27

38

29

< 25

32

25

< 33

27

26

< 35

32

23

< 18

< 24

< 33

< 38

31

23

<9

<8

<5

<7

< 10

<8

<9

< 10

<8

12

< 12

<7

<12

<9

<4

<5

<7

<11

< 13

<6

- 01/27/14

- 03/04/14

- 04/01/14

- 04/29/14

- 06/03/14

- 07/01/14

- 07/29/14

- 09/02/14

- 09/29/14

- 10/28/14

- 12/02/14

- 12/29/14 MEAN

Table C-II1.1 CONCENTRATIONS OF GAMMA EMITTERS IN PREDATOR AND BOTTOM FEEDER (FISH)

SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION PERIOD K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 1-131 Cs-134 Cs-1 37 16C5 PREDATOR 05/27/14 11/25/14 MEAN 16C5 BOTTOM FEEDER 05/27/14 11/25/14 MEAN 29C1 PREDATOR 05/22/14 10/19/14 MEAN 29C1 BOTTOM FEEDER 05/22/14 10/19/14 5702 +/- 848

< 40 4113 +/- 1162

< 74 4908 +/- 2247 3169 +/- 609

< 45 3390 +/- 1009

< 62 3280 +/- 313 3123 +/- 786

< 50 3835 +/- 720

< 52 3479 +/- 1007 3402 +/- 841

< 61 3967 +/- 1035

< 48

< 62

< 87

< 105

< 162

< 49

< 81

< 106

< 172

< 185

< 159

< 52

< 80

<54

< 93

< 42

< 57

< 98

< 92

< 50

< 61

< 101

< 126

< 163

< 103

< 45

< 42

< 46

< 50

< 65

< 63

< 146

< 147

< 65

<54

< 112

< 105

< 359

< 2119

< 62

< 44

< 57

< 56

< 63

< 75

< 138

< 154

< 67

< 55

< 141

< 108

< 357

< 3326

< 71

< 47

< 62

< 66 MEAN 3685 +/- 799

Table C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/KG DRY +/-2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Co-60 1-131 Cs-134 Cs-137 PERIOD 16B2 06/11/14 1181 +/- 712 15450 +/- 1772

< 87

< 100

< 83

< 181

< 76 178 +/- 71 12/08/14

< 777 15580 +/- 2068

< 88

< 86

< 104

< 140

< 84

< 121 MEAN 15515 +/- 184 16C4 06/11/14 3587 +/- 1011 14160 +/- 1906

< 80

< 76

< 112

< 209

< 85 163 +/- 110 12/08/14

< 956 16970 +/- 2246

< 102

< 107

< 110

< 177

< 96 133 +/- 84 MEAN 15565 +/- 3974 148 +/- 43 33A2 06/11/14

< 766 10740 +/- 1374

< 85

< 83

< 59

< 168

< 73

< 96 12/08/14

< 739 14110 +/- 1875

< 94

< 84

< 82

< 160

< 85

< 87 MEAN 12425 +/- 4766

Table C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA r-COLLECTION PERIOD 12/30/13

-01/06/14 01/06/14 -01/13/14 01/13/14 -01/20/14 01/20/14 -01/27/14 01/27/14 -02/04/14 02/04/14

-02/10/14 02/10/14

-02/17/14 02/17/14

-02/24/14 02/24/14

-03/02/14 03/02/14

-03/10/14 03/10/14

-03/16/14 03/16/14

-03/24/14 03/24/14

-03/31/14 03/31/14

-04/07/14 04/07/14

-04/14/14 04/14/14

-04/21/14 04/21/14

-04/28/14 04/28/14

-05/05/14 05/05/14

-05/12/14 05/12/14

-05/19/14 05/19/14 - 05/27/14 05/27/14 - 06/02/14 06/02/14 - 06/09/14 06/09/14 - 06/16/14 06/16/14 - 06/23/14 06/23/14 - 06/30/14 06/30/14 - 07/07/14 07/07/14 - 07/14/14 07/14/14 - 07/21/14 07/21/14 - 07/28/14 07/28/14 - 08/04/14 08/04/14 - 08/11/14 08/11/14 - 08/18/14 08/18/14 - 08/25/14 08/25/14 - 09/02/14 09/02/14 - 09/08/14 09/08/14 - 09/15/14 09/15/14 - 09/22/14 09/22/14 - 09/30/14 09/30/14 - 10/07/14 10/07/14 - 10/13/14 10/13/14 - 10/20/14 10/20/14 - 10/27/14 10/27/14 - 11/03/14 11/03/14 - 11/10/14 11/10/14 - 11/18/14 11/18/14 - 11/24/14 11/24/14 - 12/01/14 12/01/14 - 12/08/14 12/08/14 - 12/15/14 12/15/14 - 12/22/14 12/22/14 - 12/29/14 GROUP I I

GROUP 11 1 US3 13 +/- 5 17 +/- 5 20 +/- 5 17 +/-5 16 +/-5 29 +/-7 23 +/-5 15 +/-5 31 +/-7 19 +/-5 18 +/-6 8+/-5 20 +/-5 16 +/-5 19 +/-5 19 +/-5 15 +/-5 7+/-5 7+/-4 9+/-4 19 +/-5 11 +/-6 7+/-4 9+/-4 13 +/-5 14 +/-5 13 +/-5 15 +/-5 9+/-5 14 +/-3 10 +/-3 11 +/-5 11 +/-5 8+/-5 10 +/-4 18 +/-6 12 +/-5 20 +/-5 19 +/-5 13 +/-5 18 +/-6 17 +/-6 14 +/-5 14 +/-5 15 +/-4 19 +/-6 19 +/-5 19 +/-6 13 +/-5 17 +/-5 7+/-5 l1b1 22 +/- 5 18 +/- 5 22 +/- 6 16 +/- 5 19 +/- 5 26 +/- 7 26 +/- 6 14 +/-5 27 +/-7 16 +/-5 15 +/-6

<7 18 +/-5 10 +/-5 16 +/-5 16 +/-5 8+/-5 8+/-5 17 +/-5 13 +/-5 14 +/-5

< 8 11 +/-5 8+/-4 15 +/-5 14 +/-5 17 +/-5 16 +/-5 11 +/-2 10 +/-5 11 +/-4 17 +/-5 11 +/-5 10 +/-5 12 +/-4 15 +/-6 14 +/-5 24 +/-5 22 +/-5 11 +/-5 18 +/-6 11 +/-5 8+/-5 14 +/-5 14 +/-5 12 +/-4 13 +/-6 19 +/-5 14 +/-5 14 +/-5 17 +/-5 10 +/-5 13~S4 14611 19 +/- 5 20 +/- 5 19 +/- 6 22 +/- 6 20 +/- 5 25 +/- 7 19 +/- 5 16 +/- 5 25 +/- 7 21 +/- 5 16 +/- 6 10 +/- 5 21 +/- 6 8+/-5 14 +/-5 16 +/-5 13 +/-5

<7 18 +/-5 19 +/- 5 19 +/- 5 9+/-6 12 +/-5 10 +/-5 15 +/-5 15 +/-5 19 +/-5 16 +/-5 9+/-5 15 +/-5 12 +/-4 13 +/-5 11 +/-5 13 +/-5 9+/-4 16 +/-6 15 +/-5 21 +/-5 (2) 19 +/-5 14 +/-5 21 +/-6 10 +/-5 11 +/-5 18 +/-5 13 +/-5 13 +/-4 17 +/-6 16 +/-5 18 +/-5 10 +/-5 19 +/-5 10 +/-5 I GROUP III 6C1 19 +/- 5 20 +/- 5 21 +/- 6 11 +/-5 16 +/-5 26 +/-6 26 +/-6 16 +/-5 21 +/-7 18 +/-5 16 +/-6 9+/-5 14 +/-5 11 +/-5 17 +/-5 18 +/-5 12 +/-5 8+/-5 19 +/-5 18 +/-5 19 +/-5 13 +/-6 9+/-5 9+/-4 16 +/-5 15 +/-5 19 +/-5 19 +/-5 10 +/-5 14 +/-6 10 +/-4 14 +/-5 13 +/-5 14 +/-5 13 +/-5 18 +/-6 15 +/-5 21 +/-5 21 +/-5 13 +/-5 20 +/-6 12 +/-5 15 +/-5 17 +/- 5 12 +/- 5 17 +/-5 18 +/-6 21 +/-5 17 +/-6 18 +/-6 12 +/-5 14 +/-5 1501 23 +/- 5 20 +/- 5 19 +/- 5 13 +/- 5 18 +/- 5 26 +/- 6 26 +/- 6 17 +/-5 23 +/-7 20 +/-5 18 +/-6 9+/-5 17 +/-5 14 +/-5 17 +/-5 19 +/-5 11 +/-5 8+/-5 17 +/-5 11 +/-5 17 +/-5 9+/-5 11 +/-5 13 +/-5 10 +/-5 15 +/-5 15 +/-5 9+/-5 9+/-5 13 +/-4 15 +/-5 9+/-5 10 +/-5 10 +/-4 20 +/-6 15 +/-5 21 +/-5 18 +/-5 12 +/-5 24 +/-6 12 +/-5 9+/-5 13 +/-5 17 +/-5 6+/-4 13 +/-6 20 +/- 5 17 +/- 5 14 +/- 5 16 +/- 5 14 +/- 5 2261 19 +/- 5 19 +/- 5 24 +/- 6 17 +/- 5 21 +/- 5 58 +/- 15 22 +/- 5 14 +/- 5 (1) 17 +/- 5 19 +/- 6 10 +/- 5 20 +/- 5 12 +/- 5 14 +/-5 21 +/-5 12 +/-5

< 7 22 +/-5 17 +/-5 12 +/- 4

< 8 14 +/- 5 9+/-4 22 +/-5 12 +/-5 20 +/-8 (1)

(1)

(1) 8+/-4 17 +/- 4 13 +/- 4 21 +/- 5 9+/-4 9+/-4 13 +/-4 7+/-4 12 +/-4 10 +/-5 7+/-4 15 +/-5 12 +/-5 15 +/-4 9+/-4 MEAN 15 +/-10 15 +/-10 12 +/-8 16 +/-9 16 +/-8 15 +/-10 17 +/-17 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION (2) SEE PROGRAM CHANGES SECTION FOR EXPLANATION C-8

Table C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I - ON-SITE LOCATIONS GROUP II - INTERMEDIATE DISTANCE LOCATIONS GROUP III - CONTROL LOCATIONS COLLECTION PERIOD MIN MAX MEAN +

2SD COLLECTION PERIOD MIN MAX MEAN+/-

2S.

COLLECTION PERIOD MIN MAX MEAN+/-

2SQ HO -

U11f4 fln I H

L I

Z I(JU O

W"IUl I1'4 IJ rz IZ7 +/-

U I-IOPII0J U1.14UII Ilt II 0

4 O

0 I

IfIJUIIo -

UzJ'tIlt It f"

Zu +/-

02/04/14 03/02/14 03/31/14 04/28/14 06/02/14 06/30/14 08/04/14 09/02/14 09/30/14 11/03/14 12/01/14 03/02/14 03/31/14 04/28/14 06/02/14 06/30/14 08/04/14 09/02/14 09/30/14 11/03/14 12/01/14 12/29/14 14 8

8 7

7 9

8 12 8

7 7

31 21 19 19 15 19 17 24 21 19 19 23 17 14 13 12 13 11 18 14 14 14

+12

+/-9

+/-8

+/-10

+6

+/-6

+/-5

+/-7

+/-8

+/-7

+8 02/04/14 03/02/14 03/31/14 04/28/14 06/02/14 06/30/14 08/04/14 09/02/14 09/30/14 11/03/14 12/01/14 03/02/14 03/31/14 04/28/14 06/02/14 06/30/14 08/04/14 09/02/14 09/30/14 11/03/14 12/01/14 12/29/14 16 9

11 8

9 9

9 15 9

6 12 26 20 19 19 16 19 15 21 24 21 18 23 15 15 14 12 13 12 18 15 15 15

+8

+/-9

+/-7

+/-9

+/-5

+/-8

+/-4

+/-6

+/-9

+/-10

+/-4 02/04/14 03/02/14 03/31/14 05/05/14 06/02/14 06/30/14 08/04/14 09/02/14 09/30/14 11/03/14 12/01/14

- 02/24/14

- 03/31/14

- 04/28/14

- 05/27/14

- 06/30/14

- 07/07/14

- 09/02/14

- 09/30/14

- 11/03/14

- 12/01/14

- 12/29/14 14 10 12 12 9

20 8

13 8

58 20 21 22 22 20 22 17 16 31 +/- 47 16 +/- 9 15 +/- 9 17 +/- 10 14 +/- 11 20 +/- 0 14 +/- 11 15 +/- 3 12 +/- 7 12/30/13 - 12/29/14 7

31 15 +/- 10 12/30/13 - 12/29/14 6

26 15 +/-9 12/30/13 - 12/29/14 8

58 17 +/- 17

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION PERIOD Be-7 Mn-54 Co-58 Co-60 Cs-1 34 Cs-137 10S3 12/30/13 03/31/14 06/30/14 09/30/14 MEAN 11SI 12/30/13 03/31/14 06/30/14 09/30/14 MEAN 13S4 12/30/13 03/31/14 06/30/14 09/30/14

- 03/31/14

- 06/30/14

- 09/30/14

- 12/29/14

- 03131/14

- 06/30/14

- 09/30/14

- 12/29/14 56 71 59 40

+/- 28

+/- 24

+/-34

+/- 21 56 +/- 26

<4

<2

<5

<2

<3

<1 59 81 79 53 t 21

+/- 26

+/- 25 68 +/- 28

- 03/31/14

- 06/30/14

- 09/30/14

- 12/29/14 (1) 55 +/- 20

< 2 MEAN 55 +/- 0

<5

<4

<6

<2

<3

<5

<2

<4

<6

<4

<3

<4

<5

<2

< 41

<5

<4

<3

<2

<3

<2

<3

<2 14S1 12/30/13 03/31/14 06/30/14 09/30/14 MEAN 15D1 12/30/13 03/31/14 06/30/14 09/30/14

- 03/31/14

- 06/30/14

- 09/30/14

- 12/29/14

- 03/31/14

- 06/30/14

- 09/30/14

- 12/29/14

<4

<3

<4

<2

<3

<2

<4

<3

<4

<2

<3

<2

<2 58 59 57 45

+/- 25

+/- 39

+/- 25 55 +/- 13

<3

<4

<5

<4

<2

<3 3

3 5

3 2

2 2

3

<2

<3

<4

<3

<2

<3

<5

<3

< 12

<4

<2

<3

<4

<2

<3

<2 76 56 69 52

+/- 23

+/- 29

+/- 28

+/- 25 MEAN 63 +/- 23 22G1 12/30/13 03/31/14 06/30/14 09/30/14

- 03/31/14

- 06/30/14

- 07/07/14 (2)

- 12/29/14 55 88 568 69

+/- 42

+/- 38

+/- 326

+/-34

<4

<2

< 16

<4

<5

<2

< 14

<5

<3

< 12

<4 MEAN 195 +/- 499 6C1 12/30/13 03/31/14 06/30/14

- 03/31/14

- 06/30/14

- 09/30/14 80 88 72 51

+/- 21

+/- 25

+/- 26

+/- 27

<2

<3

<4

<3

<2

<4

<2

<3

<4

<3

<2

<3

<4

<2

<4 09/30/14 - 12/29/14 MEAN 73 +/- 32 (1) SEE PROGRAM CHANGES SECTION FOR EXPLANATION (2) FOR THE THIRD QUARTER OF 2014, THE VALUES FOR LOCATION 22G1 ARE HIGHER DUE TO MINIMAL SAMPLE VOLUME.

SAMPLE WAS NOT AVAILABLE FOR TWELVE OUT OF THIRTEEN WEEKS IN THE QUARTER AS NOTED IN THE EXCEPTIONS SECTION OF THE REPORT.

C-IU

Table C-VI.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD 12/30/13 - 01/06/14 01/06/14 - 01/13/14 01/13/14 - 01/20/14 01/20/14 - 01/27/14 01/27/14 - 02/04/14 02/04/14 - 02/10/14 02/10/14 - 02/17/14 02/17/14 - 02/24/14 02/24/14 - 03/02/14 03/02/14 - 03/10/14 03/10/14 - 03/16/14 03/16/14 - 03/24/14 03/24/14 - 03/31/14 03/31/14 - 04/07/14 04/07/14 - 04/14/14 04/14/14 - 04/21/14 04/21/14 - 04/28/14 04/28/14 - 05/05/14 05/05/14 - 05/12/14 05/12/14 - 05/19/14 05/19/14 - 05/27/14 05/27/14 - 06/02/14 06/02/14 - 06/09/14 06/09/14 - 06/16/14 06/16/14 - 06/23/14 06/23/14 - 06/30/14 06/30/14 - 07/07/14 07/07/14 - 07/14/14 07/14/14 - 07/21/14 07/21/14 - 07/28/14 07/28/14 - 08/04/14 08/04/14 - 08/11/14 08/11/14 - 08/18/14 08/18/14 - 08/25/14 08/25/14 - 09/02/14 09/02/14 - 09/08/14 09/08/14 - 09/15/14 09/15/14 - 09/22/14 09/22/14 - 09/30/14 09/30/14 - 10/07/14 10/07/14 - 10/13/14 10/13/14 - 10/20/14 10/20/14 - 10/27/14 10/27/14 - 11/03/14 11/03/14 - 11/10/14 11/10/14 - 11/18/14 11/18/14 - 11/24/14 11/24/14 - 12/01/14 12/01/14 - 12/08/14 12/08/14 - 12/15/14 12/15/14 - 12/22/14 12/22/14 - 12/29/14 10S3

55

< 66

< 45

< 58

< 29

< 68

< 47

< 55

25

32

< 60

< 45

< 47

< 42

<44

<34

< 48

57

< 49

< 58

18

< 63

<34

< 50

< 61

< 59

<54

< 60

< 62

< 48

< 20

< 47

25

< 47

52

< 66

< 67

< 69

< 36

< 67

< 68 (1)

12

20

46

32

< 49

52

35

65

65

51 GROUP I 13S4 1151

57

< 68

47

< 60

30

< 69

< 48

56

< 67

33

< 62

< 47

< 48

< 43

< 46

35

50

59

51

< 60

< 44

< 65

14

52

< 61

59

55

< 60

< 62

< 48

51

< 47

13

47

53

< 67

< 68

70

37

< 68

< 69

< 66

20

18

32

50

53

35

< 66

65

51 14S1

50

62

62

69

< 36

< 63

50

< 67

68

< 34

61

< 45

57

52

65

36

37

63

55

52

35

65

36

61

25

52

< 34

59

61

< 48

50

< 47

25

< 46

22

< 66

67

69

38

67

< 67

68

65

20

< 46

32

27

52

35

< 65

< 64

51 GROUP 11 6C1 1501

< 56

< 49

< 67

< 60

< 46

< 60

< 67

< 30

< 35

< 67

< 60

<47

< 49

<55

< 65

< 66

< 33

< 61

< 59

< 46

< 43

< 47

< 55

< 43

< 50

< 45

< 63

<34

< 36

< 49

< 36

< 58

< 61

< 19

< 54

< 58

< 50

< 43

< 34

< 63

< 62

< 34

<51

< 59

< 62 (1)

< 60

< 61

< 55

< 14

< 61

< 25

< 24

< 62

< 49

< 19

<51

< 50

< 48

< 47

< 25

<47

< 25

< 53

< 36

< 66

< 68

< 26

< 38

< 70

< 37

< 38

< 68

< 65

< 29

< 68

< 69

< 58

< 67

< 8

<21

< 25

< 47

< 55

< 32

< 33

<50

< 68

< 53

< 35

< 42

< 66

< 69

< 66

< 58

< 52

< 35 IGROUP III 22G1

50

< 61

< 60

< 68

35

22

50

< 65 (1)

< 34

60

44

55

51

< 64

< 36

15

< 62

55

51

35

< 63

36

< 60

< 61

53

< 64 (1)5 (1)8 (1)8 (1)

(1)5 (1)5 (1)3

65

25

33

17 (2)

< 62

55

48

< 64

21

< 46

27

56

< 46

< 34

60

< 49

30 MEAN--

(1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION (2) SEE PROGRAM CHANGES SECTION FOR EXPLANATION C-1 I

Table C-VII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROL FARM 36E1 I

INDICATOR FARM 25C1 COLLECTION PERIOD 01/15/14 02/11/14 02/17/14 03/12/14 04/01/14 04/15/14 04/29/14 05/13/14 05/27/14 06/10/14 06124/14 07/08/14 07/22/14 08/05/14 08/19/14 09/02/14 09/16/14 09/30/14 10/14/14 10/28/14 11/11/14 11/24/14 12/09/14 23F1 18E1 19B1

< 0.7

< 0.5

< 0.7

< 0.5

< 0.9

< 0.6

< 0.7

< 0.4

< 0.5

< 0.4

< 0.5

< 0.6

< 0.7

< 0.4

< 0.5

< 0.7

< 0.9

< 0.7

< 0.6

< 0.8

< 0.9

< 0.7

< 0.6

< 0.8

< 0.5

< 0.9

< 0.7

< 0.3

< 0.5

< 0.6

< 0.5

< 0.6

< 0.7

< 0.9

< 0.4

< 0.8

< 0.9

< 0.7

< 0.6

< 0.7

< 0.5

< 0.8

< 0.6

< 0.7

< 0.3

< 0.5

< 0.7

< 0.5

< 0.7

< 0.8

< 0.4

< 0.8

< 0.7

< 0.9

< 0.5

< 0.7

< 0.7 6.5

+

< 0.4

< 0.5

< 0.7

< 0.8

< 0.5

< 0.7

< 0.8

< 0.7

< 0.8

< 0.7 1.9 (1)

MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-I2

Table C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION PERIOD 18E1 01/15114 02/17/14 03/12/14 04101114 04115/14 04/29/14 05/13/14 05/27/14 06/10/14 06/24/14 07108/14 07/22/14 08/05/14 08/19/14 09/02/14 09/16/14 09/30/14 10/14/14 10/28/14 11/11/14 11/24/14 12/09/14 MEAN 19B1 01/14/14 02/11/14 03/11/14 04/01/14 04/15/14 04/29/14 05/13/14 05/27/14 06/10/14 06/24/14 07/08/14 07/22/14 08/05/14 08/19/14 09/02/14 09/16/14 09/30/14 10/14/14 10/28/14 11/11/14 11/24/14 12/09/14 MEAN K-40 Cs-134 Cs-137 Ba-140 La-140 1254 1167 1307 1329 1230 1157 1509 1392 1333 1342 1502 1253 1158 1263 1077 1196 1205 1197 1128 1139 1177 1176

+/- 160

+/- 136

+/- 126

+/- 136

+/- 148

+/- 112

+/- 165

+/- 150

+/- 167

+/- 144

+/- 188

+/- 105

+/- 133

+/- 114

+/- 141

+/- 107

+/- 117

+/- 130

+/- 160

+/- 177

+/- 119

+/- 140 1250 +/- 229 1389 +/- 139 1292 +/- 135 1222 +/- 124 1172 +/- 141 1197 +/- 157 1242 +/- 158 1330 +/- 144 1336 +/- 151 1164 +/- 157 1247 +/- 142 1422 +/- 159 1315 +/- 116 1349 +/- 125 1381 +/- 167 1292 +/- 146 1210 +/- 81 1271 +/- 147 1342 +/- 191 1081 +/- 141 1128 +/- 131 1234 +/- 173 1240 +/- 179 1266 +/- 176

<7

<6

<5

<4

<7

<5

<6

<5

<6

<4

<5

<4

<7

<4

<3

<5

<6

<7

<5

<4

<7

<6

<7

<8

<6

<8

<4

<6

<3

<6

<7

<9

<5

<6

<7

<6

<7

<6

<4

<8

<5

<9

<5

<8

<5

<8

<5

<8

<5

<6

<7

<9

<5

<7

< 47

< 24

< 30

< 33

< 29

< 31

< 32

< 39

< 28

< 37

< 17

< 35

< 26

< 60

< 21

< 26

< 28

< 33

< 42

< 28

< 25

< 52

< 32

< 22

< 35

< 38

< 37

< 34

< 40

< 39

< 36

< 30

< 39

< 27

< 33

< 43

< 15

< 47

< 36

< 43

< 24

< 47

< 28

< 14

<8

<5

<8

<6

<8

<9

< 12

<9

<6

< 11

<8

< 12

<6

< 10

< 13

<8

<5

< 14

<8

<6

<9

< 12

<6

< 13

< 14

<8

<9

< 14

<3

< 12

<8

< 10

< 13

< 11

<6

<5

<8

<6

<7

<8

< 10

<8

<7

<8

<6

<3

<7

<8

< 10

<5

<8

<8 C-13

Table C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION PERIOD 23F1 01/14/14 02/11/14 03/11/14 04/01/14 04/15/14 04/29/14 05/13/14 05/27/14 06/10/14 06/24/14 07/08/14 07/22/14 08/05/14 08/19/14 09/02/14 09/16/14 09/30/14 10/14/14 10/28/14 11/11/14 11/24/14 12/09/14 MEAN 25C1 01/14/14 02/11/14 03/11/14 04/01/14 04/15/14 04/29/14 05/13/14 05/27/14 06/10/14 06/24/14 07/08/14 07/22/14 08/05/14 08/19/14 09/02/14 09/16/14 09/30/14 10/14/14 10/28/14 11/11/14 11/24/14 12/09/14 MEAN K-40 Cs-134 Cs-137 Ba-140 La-140 1403 1344 1320 1216 1223 1359 1382 1264 1392 1118 1345 1186 1318 1367 1190 1204 1407 1268 1260 1234 1357 1259 143 142 134 105 137 129 154 118 141 136 149 118 169 161 131 110 123 138 173 176 144 135 1292 +/- 164

<6

<5

<7

<4

<5

<6

<5

<6

<9

<5

<6

<5

<4

<6

.< 11

<6

<5

<6

<5

<6

<5

<7

<6

<7

<5

<6

<3

<7

<5

<7

<5

<7

<6

<7

<5

<6

<8

<5

<7

<6

<9

<6

<7

<5

<6

<8

< 11

<7

<6

<7

<6

<7

<6

<7

<8

<4

<6

<5

<6

<3

<8

<6

<7

<6

< 50

< 32

< 35

< 24

< 29

< 32

< 27

< 40

< 35

< 37

< 26

<34

< 38

< 23

< 35

< 28

< 42

< 54

<34

< 21

< 40

< 30

< 31

< 34

< 26

< 48

< 26

< 32

< 40

< 39

< 33

< 22

< 33

< 26

< 46

< 13

< 44

< 36

< 30

<34

< 37

< 21

< 14

< 11

< 10

<7

<8

<9

<8

<7

< 12

<5

< 10

<9

< 12

<7

<8

<7

< 12

< 14

<8

<6

< 15

< 11

<8

< 10

<8

<6

<9

<8

<9

<8

< 13

<8

<11

<3

< 14

<9

10

< 13

<9

<6 1220 1316 1156 1178 1259 1195 1313 1345 1404 1303 1342 1202 1301 1398 1234 1240 1332 1372 1280 1237 1130 1288 156 132 163 148 125 176 160 154 183 140 179 129 178 122 120 77 157 172 116 165 120 124 1275 +/- 153 C-I4

Table C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD 36E1 01/14/14 04101/14 07/08/14 10/14/14 MEAN 1068 +/- 122 968 +/- 131 1081 +/- 126 1202 +/- 76 1080 +/- 192

<4

<6

<5

<3

<5

<6

<4

<3

< 55

< 34

< 27

< 33

< 15

< 13

<7

< 10 C-15

TABLE C-VIII.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN BROAD LEAFY VEGETATION SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION PERIOD 11S3 06/17/14 Cat 06/17/14 Coil 06/17/14 Swi 07/15/14 Cat 07/15/14 Coil 07/15114 Swi 08/21/14 Cat 08/21/14 Coil 08/21/14 Swi 09/09/14 Cab 09/09/14 Coil 09/09/14 Swi 10/09/14 Cat 10/09/14 Coil 10109f14 Swi SR-89 SR-90 Be-7 K-40 Mn-54 Co-58 Co-60 1-131 Cs-134 Cs-137 Ra-226 Th-228 Th-232 Sbage ards ss Chard bage ards ss Chard 0bage ards ss Chard bage ards ss Chard

bage ards ss Chard

<13

13

10

<19

16

< 21

< 18

< 16

14

14

<13

< 10

<8

< 18

< 13

< 3.2 6.8

< 2.5 4.5 2.3

< 2.9

< 2.0

< 3,3

< 4.0 5.1

< 3,2 4.3

<1.9

< 3.4 3.5

- 127 1 1.7 < 229 310 + 176

+ 1.5 < 77 t 1.2 < 153

< 241

< 170

< 173 289 +/- 163 1 2,0 < 180

< 256

+ 1.5 < 260

< 159 335 +/- 142

+/- 1.5 359 +/- 169 4oq 9 377 5386 +/- 566 9455 +/- 553 2074 +/- 199 4922

388 6219 +/- 619 2188 1 325 5927 +/- 468 6467 +/- 461 2227 +/- 374 5754 +/- 595 7178 +/- 516 2417 +/- 326 4624 +/- 398 6591 +/- 553 5085 +/- 4250

< 14

< 23

<18

<9

< 16

< 26

16

< 19

< 22

< 21

< 25

< 16

15

19 MEAN 4.4 +/- 3.0 323 +/- 61

< I3

< 24

< 20

<8

< 18

26

< 15

< 16

< 22

< 20

< 26

17

16

22

< 20

< 23

< 30

<18

< 21 c 17

< 14

< 23

17

<15

25

< 35

22

< 21

21

< 14

< 23

22

<9

< 20

<36

< 21

< 24

< 23

< 28

< 35

18

< 19

< 26

< 23

< 26

< 29

< 21

< 27

< 21

< 20

< 24

< 20

< 18

< 38

< 37

< 25

< 22

< 26

<43

< 30

< 15

< 30

< 38

< 57

58

< 58

< 41

<54

< 59

< 46

< 47

< 60

< 50

< 45

< 57

< 33

< 31

< 53

< 60

< 59

<34

< 57

< 60

< 59

< 49

< 60

< 14

<-23

< 18

<7

<15

< 23

< 16

< 17

< 16

< 25

29

< 15

< 14

< 17

< 22

< 23

< 26

<18

< 17

< 19

< 16

< 17

16

< 16

< 28

< 25

17

< 17

21

< 13

24

20

<8

16

25

18

<18

< 21

< 20

<24

27

< 16

16

< 20

19

27

< 31

<18

< 23

<18

18

< 20

17

< 16

< 27

< 32

< 22

< 17

24

< 3*UU

536

< 436

< 236

< 407

< 498

< 425

< 439

< 328

< 427

< 646

673

< 394

350

< 477

< 28 38

<34 15

< 33

<39

< 35

31

< 33

< 47

< 49

< 31

< 33

< 39

< 58

< 82

< 37

< 70

103

< 62

81

< 79

85

< 110

< 102

< 71

< 78

< 87

< 77

113

129

< 68

< 76

< 70

< 69

< 68

< 67

<66

< 103

139

87

< 75

< 91 13S3 06/17/14 06/17/14 06/17/14 07/15/14 07/15114 07/15/14 08/21/14 08/21/14 08/21/14 09/09/14 09/09/14 09/09/14 10/09/14 10109/14 10/09/14 Cabbage Collards Swiss Chard Cabbage Collards Swiss Chard Cabbage Collards Swiss Chard Cabbage Collards Swiss Chard Cabbage Collards Swiss Chard e 16

21

< 14

< 20

< 13

<10

23

< 15

< 11

< 10

<9

<11

<9

< 2.3

< 2.8

<2.1

< 3.7

< 3.4

1.7

< 4.3

<2.1

< 2.3

2.6

< 1.9

<2.0

<2,3

< 2.8

< 240

< 214 365 +/- 292

< 160

165

187

< 140

< 220 277 +/- 209

143

246

< 314

187 489 +/- 154 368 +/- 174 4458 +/- 479

< 21 5434 +/- 594

< 19 5371 +/- 740

< 29 2456 +/- 360

< 18 6171 +/- 546

< 20 7571 +/- 495

< 18 2229 +/- 295

< 13 6615 +/- 560

< 19 6899 +/- 404

< 16 2661 +/- 316

< 16 5268 +/- 561

< 28 5927 +/- 663

< 35 2944+/-

404 < 21 5406 +/- 488

< 18 5944 +/- 424

< 23

< 601

< 570 1417 +/- 638

<448

< 475 2107 +/- 676 457 +/- 377

< 524 1752 +/- 356

366 713 +/- 446 1543 +/- 633

< 369 1541 +/- 429 952 +/- 510 1310 +/- 1112

< 57

< 49

<49

<36

< 33

38 43 +/- 37

< 38

< 34

< 28

< 49

< 51

< 33

31

< 38 MEAN 375 +/- 174 5024 +/- 3408

TABLE C-VIII.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN BROAD LEAFY VEGETATION SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION PERIOD 31G1 06/17/14 Cat 06/17/14 Coil 06/17/14 Swi 07/15/14 Kal 07/15/14 Swi 07/15/14 Zuc 08/21/14 Kal 08/21/14 Swi 08/21/14 Zuc 09/09/14 Cat 09/09/14 Kal 09/09/14 Swi 10/09/14 Cat 10/09/14 Kal 10/09/14 Swi SR-89 SR-90 Be-7 K-40 Mn-54 Co-58 Co-60 1-131 Cs-134 Cs-137 Ra-226 Th-228 Th-232 bage ards ss Chard e

ss Chard chini Leaves e

ss Chard chini Leaves bage e

ss Chard bage ess Chard

13

< 22

<9

14

19

15

14

13

14

<8

19

13

12

13

10 5.8 +/- 2.2 5.4 +/- 2.6

1.7

3.0

2.3

<2.5

< 4.3

2.0 4.9 +/- 2.2

2.0

< 4.4 4.4 +/- 2.5

1.9

<2.1

< 2.4

168

228 400 +/- 181

< 132 220 +/- 137 744 +/- 124 200 +/- 110

177 1335 +/- 242

288 195 +/- 103 192 +/- 148

157

234 415 +/- 182 3466 +/- 418 5572 +/- 590 10280 +/- 638 5107 +/- 377 6985 +/- 406 5839 +/- 303 5387 +/- 378 7348 +/- 552 5110 +/- 447 6358 +/- 653 7095 +/- 373 7342 +/- 571 2880 +/- 350 7836 +/- 542 9141 +/- 675 6383 +/- 3913

< 16

< 25

< 23

14

<12

<11

< 15

< 18

< 19

<21

<11

<19

<18

20

19

16

27

< 22

14

13

<11

<18

23

17

< 24

13

22

18

21

< 21

16

24

< 24

< 17

< 20

14

18

31

22

< 31

< 16

29

14

< 26

< 27

< 30

< 42

< 44

< 24

< 21

< 59

< 58

60

< 29

< 43

< 52

< 59

< 14

< 22

< 24

<13

12

<11

< 14

< 18

< 15

< 24

12

20

18

<18

17

18

< 26

< 24

15

16

<11

16

21

<17

23

12

21

<17

22

23

< 335

< 459

< 559

< 287

< 331

269

< 397

438

< 423

< 730 575 +/- 260

< 415

< 455 496 +/- 475

< 505

32

<34

< 40

28

26

21

< 33

31

< 31

< 57

25

< 33

< 35

< 39

48

< 77

117

< 89

< 59

62

50

<64

< 79

88

98

< 49

< 79

< 74

< 76

100 r)

MEAN 5.1 +/- 1.2 463 +/- 800 535 +/- 112 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

Table C-IX.I QUARTERLY DLR RESULTS FOR LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF MILLIROENTGEN/QUARTER +/-2 STANDARD DEVIATIONS STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT - DEC CODE

+/- 2 S.D.

2E1 6.3 +/- 2.5 5.5 +/- 2.4 7.0 +/- 1.7 5.1 +/- 2.7 7.7 +/- 1.8 3S1 6.1 +/- 3.4 5.1 +/- 2.0 7.4 +/- 1.0 4.2 +/- 4.2 7.6 +/- 1.8 4E1 4.3 +/- 3.1 3.8 +/- 0.4 5.1 +/- 0.8 2.4 +/- 1.2 6.0 +/- 0.4 5H1 7.8 +/- 3.1 6.3 +/- 0.6 8.9 +/- 1.0 6.6 +/- 2.4 9.3 +/- 0.9 5S1 7.1 +/- 3.6 5.9 +/- 1.6 8.9 +/- 1.2 5.2 +/- 2.1 8.4 +/- 1.7 6C1 6.1 +/- 2.5 5.2 +/- 0.6 6.7 +/- 2.1 4.8 +/- 2.8 7.5 +/- 1.5 7E1 6.5 +/- 2.8 5.7 +/- 0.3 7.3 +/- 1.1 5.0 +/- 3.0 8.1 +/- 1.3 7S1 6.5 +/- 2.6 5.7 +/- 0.2 7.5 +/- 1.1 5.1 +/- 3.0 7.7 +/- 1.2 9Cl 6.1 +/- 2.9 5.1 +/- 0.6 7.5 +/- 1.6 4.6 +/- 1.1 7.2 +/- 1.8 10E1 6.7 +/- 3.0 6.0 +/- 1.2 7.5 +/- 1.1 4.9 +/- 2.3 8.2 +/- 1.3 10F3 5.9 +/- 3.9 4.3 +/- 1.2 7.0 +/- 1.7 4.2 +/- 1.6 8.1 +/- 1.6 10S3 6.4 +/- 3.0 5.8 +/- 1.0 7.2 +/- 2.1 4.5 +/- 1.4 7.9 +/- 1.3 11S1 7.5 +/- 2.9 6.5 +/- 0.3 8.5 +/- 1.1 5.9 +/- 1.4 8.9 +/- 2.7 13C1 4.5 +/- 3.5 4.3 +/- 1.0 5.3 +/- 1.4 2.1 +/- 1.3 6.1 +/- 0.3 13E1 6.4 +/- 3.0 5.7 +/- 0.1 7.5 +/- 1.4 4.7 +/- 1.4 7.8 +/- 1.4 13S2 9.3 +/- 3.7 8.8 +/- 1.9 10.6 +/- 1.9 6.9 +/- 3.1 10.9 +/- 1.5 14S1 5.7 +/- 3.1 5.0 +/- 0.3 6.6 +/- 1.6 3.8 +/- 2.2 7.2 +/- 1.4 15D1 6.8 +/- 2.7 6.3 +/- 1.4 7.6 +/- 1.3 5.1 +/- 1.4 8.1 +/- 1.2 16F1 6.4 +/- 3.2 5.4 +/- 0.9 7.2 +/- 1.4 4.7 +/- 2.1 8.2 +/- 1.1 17B1 5.9 +/- 3.5 5.4 +/- 0.2 6.6 +/- 1.4 3.7 +/- 2.3 7.8 +/- 2.1 18S2 6.7 +/- 2.9 5.8 +/- 0.4 7.7 +/- 1.4 5.1 +/- 1.2 8.1 +/- 2.3 19D1 5.8 +/- 2.8 5.4 +/- 1.0 6.4 +/- 1.0 4.0 +/- 1.4 7.2 +/- 0.8 20D1 5.4 +/- 3.6 4.5 +/- 0.3 6.6 +/- 1.2 3.3 +/- 1.6 7.1 +/- 2.3 20F1 6.0 +/- 3.1 5.4 +/- 0.5 6.9 +/- 1.5 4.0 +/- 2.2 7.5 +/- 1.2 21S2 5.0 +/- 3.4 4.4 +/- 0.5 5.1 +/- 1.2 3.2 +/- 3.8 7.2 +/- 1.6 23S2 5.8 +/- 3.1 5.6 +/- 2.8 6.7 +/- 1.6 3.7 +/- 1.1 7.2 +/- 0.9 24D1 5.0 +/- 3.6 4.5 +/- 1.4 6.0 +/- 1.2 2.6 +/- 2.1 6.7 +/- 0.7 25D1 5.0 +/- 3.0 4.8 +/- 0.4 5.8 +/- 0.9 3.0 +/- 4.0 6.5 +/- 1.3 25S2 5.3 +/- 3.5 4.8 +/- 1.3 6.4 +/- 1.2 3.0 +/- 2.3 6.8 +/- 1.0 26S3 5.1 +/- 3.4 4.3 +/- 0.1 6.3 +/- 1.4 3.1 +/- 2.8 6.7 +/- 1.1 28D2 5.6 +/- 2.8 5.2 +/- 1.6 6.4 +/- 1.9 3.8 +/- 3.3 7.0 +/- 1.3 29E1 5.8 +/- 2.9 5.0 +/- 1.1 6.7 +/- 1.2 4.1 +/- 2.8 7.2 +/- 1.0 29S1 5.1 +/- 3.6 4.2 +/- 0.5 6.4 +/- 4.4 3.0 +/- 3.0 6.7 +/- 1.4 31D1 7.3 +/- 2.8 6.7 +/- 0.7 8.2 +/- 0.7 5.6 +/- 3.2 8.7 +/- 0.9 31D2 6.2 +/- 3.6 5.2 +/- 0.0 7.7 +/- 0.8 4.2 +/- 2.2 7.7 +/- 0.6 31S1 6.6 +/- 3.0 6.0 +/- 0.0 7.7 +/- 1.2 4.8 +/- 2.9 8.0 +/- 1.6 34E1 5.7 +/- 3.2 4.7 +/- 0.4 6.7 +/- 0.8 4.0 +/- 3.4 7.4 +/- 1.3 34S2 6.0 +/- 2.8 5.5 +/- 1.5 6.7 +/- 0.9 4.2 +/- 2.8 7.4 +/- 1.9 36D1 5.1 +/- 3.0 4.4 +/- 0.3 5.8 +/- 3.4 3.3 +/- 3.4 6.7 +/- 1.3 36S2 6.4 +/- 3.0 6.0 +/- 0.4 7.3 +/- 1.1 4.5 +/- 2.8 7.9 +/- 1.6 C-18

Table C-IX.2 COLLECTION PERIOD JAN-MAR APR-JUN JUL-SEP OCT-DEC Table C-IX.3 MEAN QUARTERLY DLR RESULTS FOR THE SITE BOUNDARY, MIDDLE AND CONTROL LOCATIONS FOR LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF MILLIROENTGEN/QUARTER +/- 2 STANDARD DEVIATIONS OF THE STATION DATA SITE BOUNDARY MIDDLE CONTROL

+/-2 S.D.

5.6 +/- 2.2 5.2 +/-1.4 6.3 +/- 0 7.3 +/- 2.5 6.8 +/-1.6 8.9 +/- 0 4.4 +/- 2.2 4.1 +/- 1.9 6.6 +/- 0 7.8 +/- 2.1 7.4 +/- 1.4 9.3 +/- 0

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF MILLIROENTGEN/QUARTER +/- 2 STANDARD DEVIATIONS OF THE STATION DATA LOCATION SITE BOUNDARY MIDDLE CONTROL SAMPLES ANALYZED 64 92 4

PERIOD MINIMUM 3.0 2.1 6.3 PERIOD MAXIMUM 10.9 8.7 9.3 PERIOD MEAN

+/-2 S.D.

6.3 +/- 3.5 5.8 +/- 3.1 7.8 +/- 3.1 SITE BOUNDARY STATIONS - 10S3, 11S1, 13S2, 14S1, 18S2, 21S2,23S2, 25S2, 26S3, 29S1, 31S1, 34S2, 36S2, 3S1, 5S1, 7S1 MIDDLE STATIONS - 10E1, 10F3, 13C1, 13E1, 15D1, 16F1, 17B1, 19D1, 20D1, 20F1, 24D1, 25D1,28D2, 29E1,2E1, 31D1, 31D2, 34E1, 36D1,4E1, 6Cl, 7E1, 9C1 CONTROL STATIONS - 5H1 C-19

FIGURE C-1 MEAN MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2014 12 10.......---

/I A

0 1

I

,A:i:

-It 8 -.

%~-~

4 - 2 A

CONTROL]

~ --" -INDICATO R:

082 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 11 12131415 Note: 2005 analysis changed from Insoluble & Soluble to Total Gross Beta YEAR LGS CRITICALITY LGS CHANGED TO TOTAL GROSS BETA AT THE BEGINNING UNIT NO. 1: 12/22/84 OF 2005. PREVIOUS DATA INCLUDED SUMMATION OF LESS UNIT NO. 2: 08/11/89 THAN VALUES.

FIGURE C-2 MEAN ANNUAL CS-137 CONCENTRATIONS IN FISH SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2014 6-5

-u16C5

-~2OS1

~ -~29CI

.~

Note: Second half of 2000 switched to reporting < MDC when no activity was detected..

45

..... I.............

.......... Using MDC values result in a..............

.a.

larger number. LLD < 150 pCi/kg. -- --.

E ILGS CRITICALITY UNIT NO. 1: 12/22/84 UNIT NO. 2:_08/11/89

'* 25

"."i '............

CL

' ~.

5..

-5

.. i..........

82 84 86 88 90 92 94 96 98 00 02 04 06 08 10 12 14 YEAR CONTROL = 29CI Station 20S1 discontinued in 1995

FIGURE C-3 CONCENTRATIONS OF CS-137 IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2014 1400

-16B 2 LGS CRITICALITY 1

1200 UNITNO. 1: 12/22/84 6C4 UNIT NO. 2: 08111/89 LGSIR 439395 33A2_____

.CONTROL 33A2 Suc nnw 8 0 ouc nnw 100600 H

6 0 0 0.

200....

-2 0 0

-200 82 83 85 86 88 89 91 92 94 95 97 98 00 01 03 04 06 07 09 10 12 13 15 Year

FIGURE C-4 MEAN MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2014 150

--- Group I 135-

.............................- i-GroupI

-~Group III 1 2 0 IChernobyll I....i S105 E90.....

C.)

LGS CRITICALITY 60................

UNIT NO. 1: 12122184 m

I UNIT NO. 2: 08111/89 4

5 30 15 82 84 86 88 90 92 94 96 98 00 02 04 06 08 10 12 14 YEAR

FIGURE C-5 MEAN WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 2014 5-u-GROUP I

-a-- GROUP II GROUP III 40..............

1 0 0

3 6

9 12 15 18 21 24 27 30 33 36 39 42 45 48 51 WEEK NO.

FIGURE C-6 MEAN QUARTERLY AMBIENT GAMMA RADIATION LEVELS (DLR)

IN THE VICINITY OF LGS, 1985 - 2014 NOTE: Control Station 5H1 became the only distant location beginning in 1995 13 SITE 12 INTERMEDIATE.

1---CONTROL

Control 5H1-1 1 0 - -

9 8

IA...

6 6.

5 4

85 86 87 88 89 90 9192 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 1112 13 14 YEAR

Intentionally left blank

APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY

Intentionally left blank

TABLE D-1.1 CONCENTRATIONS OF TOTAL GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA COLLECTION 16C2 PERIOD 12/30/13 - 01/27/14 1.9 +/- 0.8 01/27/14 - 03/04/14 2.5 +/- 0.8 03/04/14 - 04/01/14 2.3 + 0.8 04/01/14 - 04/29/14

< 1.9 04/29/14 - 06/03/14 1.0 + 0.5 06/03/14 - 07/01/14 2.4 +/- 0.8 07101/14 - 07/29/14 1.2 +/- 0.6 07/29/14 - 09/02/14 1.8 +/- 1.0 09/02/14 - 09/29/14 3.4 +/- 1.1 09/29/14 - 10/28/14 2.4 + 1.0 10/28/14 - 12/02/14 3.5 +/- 1.2 12/02/14 - 12/29/14 2.7 +/- 0.8 MEAN 2.3 +/- 1.6 TABLE D-I.2 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA COLLECTION 16C2 PERIOD 12/30/13 - 01/27/14

< 0.2 01/27/14 - 03/04/14

< 0.4 03/04/14 - 04/01/14

< 0.4 04/01/14 - 04/29/14

< 0.5 04/29/14 - 06/03/14

< 0.1 06/03/14 - 07/01/14

< 0.5 07/01/14 - 07/29/14

< 0.2 07/29/14 - 09/02/14

< 0.5 09/02/14 - 09/29/14

< 0.4 09/29/14 - 10/28/14

< 0.4 10/28/14 - 12/02/14

< 0.4 12/02/14 - 12/29/14

< 0.3 MEAN TABLE D-I.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION 16C2 PERIOD 12/31/13 - 04/01/14

< 143 04/01114 - 07/01/14

< 142 07/01114 - 09/29/14

< 185 09/29/14 - 12/29/14

< 169 MEAN THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES D-1

TABLE D-1.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD 16C2 12/30/13

- 01/27/14

< 2

< 1

< 3

<2

< 2

<4

< 3

<4

< 3

<2

< 9

< 2 01/27/14

- 03/04/14

< 2

<2

<4

< 2

< 3

<3

< 2

< 3

<2

< 2

< 15

<2 03/04/14 -04/01/14

< 3

< 8

< 2

< 8

<4

< 3

<4

< 5

< 13

< 4 04/01/14 -04/29/14

< 2

< 1

< 5

< 2

< 3

< 2

< 3

< 14

< 2 04/29/14

- 06103/14

< 2

< 6

< 1

< 3

< 5

< 3

< 5

< 3

< 4

< 16

< 3 06/03/14 -07/01/14

< 2

< 5

<2

< 5

<5

< 3

< 8

<2

<3

< 21

<4 07/01/14 -07/29/14

< 3

< 4

< 7

< 2

< 6

< 5

< 4

< 10

< 3

< 4

< 16

< 6 07/29/14 -09/02/14

< 2

<2

< 4

<2 2

< 2

< 7

< 2

< 3

< 14

<2 09/02/14

- 09/29/14

< 3

< 2

< 5

< 3

<4

< 3

< 5

< 2

< 3

< 19

< 3 09/29/14 -

10/28/14

< 3

< 4

< 2

< 3

< 6

< 3

< 4

< 7

< 3

< 15

< 4 10/28/14 -12/02/14

< 3

< 2

< 3

< 5

< 2

< 8

< 2

< 20

< 4 12/02/14

- 12/29/14

< 1

< 2

< 3

< 1

< 3

< 2

<4

<2

< 2

< 10

<2 MEAN

TABLE D-11.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE AND 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA COLLECTION PERIOD 1/--/.SU113 UIIUt*I14 01/06/14

- 01/13/14 01/13/14

- 01/20/14 01/20/14

- 01/27/14 01/27/14

- 02/04/14 02/04/14

- 02/10/14 02/10/14 02/17/14 02/17/14 02/24/14 02/24/14 03/02/14 03/02/14 03/10/14 03/10/14 03/16/14 03/16/14 03/24/14 03/24/14 03/31/14 03/31/14 04/07/14 04/07/14 04/14/14 04/14/14 04/21/14 04/21/14 04128/14 04/28/14 05/05/14 05/05/14 -

05/12/14 05/12/14 -

05/19/14 05/19/14 -

05/27/14 05/27/14 -

06/02/14 06/02/14 -

06/09/14 06/09/14 -

06/16/14 06/16/14 -

06/23/14 06/23/14 -

06/30/14 06/30/14 -

07/07/14 07/07/14 -

07/14/14 07/14/14 -

07/21/14 07/21/14 -

07/28/14 07/28/14 -

08/04/14 08/04/14 -

08/11/14 08/11/14 -

08/18/14 08/18/14 -

08/25/14 08/25/14 -

09/02/14 09/02/14 -

09/08/14 09/08/14 -

09/15/14 09/15/14 -

09/22/14 09/22/14 -

09/30/14 09/30/14 -

10/07/14 10/07/14 -

10/13/14 10/13/14 -

10/20/14 10/20/14 -

10/27/14 10/27/14 -

11/03/14 11/03/14 -

11/10/14 11/10/14 -

11/18/14 11/18/14 -

11/24/14 11/24/14 -

12/01/14 12/01/14 -

12/08/14 12/08/14 -

12/15/14 12/15/14 -

12/22/14 12/22/14 -

12/29/14 11S2 GROSS BETA Z4, :t: 4 29 +/- 5 30 +/- 5 25 +/- 4 23 +/- 4 38 +/- 6 32 +/- 5 17 +/- 4 37 +/- 6 28 +/- 4 23 +/- 5 15 +/- 4 25 +/- 4 16 +/- 4 21 +/- 4 24 +/- 4 17 +/- 4 11 4

19 4

23 +4 18 5

14 4

12 4

22 +4 19+/- 4 18+/- 4 26 +/-4 20 +/-4 22 +/-4 19+/- 4 23 +/-4 17+/- 4 17+/- 4 22 +/-4 24 +/-5 12+/- 4 30 +/- 5 27 +/- 4 22 +/- 4 31 +/- 6 19 +/- 4 19 +/- 4 21 +/- 4 26 +/- 4 7+/-3 28 +/-6 24 +4 28 +/-4 19 4

29 +/-4 16+/- 4 11IS2 1-131

< 13

< 10

< 14

<5

< 14

< 13

< 11

< 13

< 15

< 20

< 14

< 15

< 21

<8

< 15

< 10

< 17

< 11

< 13

< 12

< 21

< 13

< 18

< 12

< 22

< 20

< 19

< 12

< 19

< 16

< 19

< 23

< 16

<8

< 18

< 17

< 10

< 16

< 18

< 11

<9

< 18

< 22

< 19

< 15

< 14

<9

< 20 MEAN 22 +/- 13 D-3

TABLE D-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION PERIOD Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137 11S2 12/30/13 -

03/31/14 03/31/14 -

06/30/14 06/30/14 -

09/30/14 09/30/14 -

12/29/14 MEAN 64 +/-

67 +/-

80 +/-

53 +/-

17 17 15 15

< 1.3

< 0.7

< 0.6

< 0.7

< 0.9

< 0.4

< 0.6

<1.1

< 1.0

< 0.8

< 0.7

< 0.3

< 0.7

< 1.0

< 0.7

< 0.5 66 +/- 22 D-4

TABLE D-Ill.1 CONCENTRATIONS OF 1-131 BY CHEMICAL SEPARATION AND GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION PERIOD 1-131 K-40 Cs-134 Cs-137 Ba-140 La-140 19B1 01/14/14 04/01/14 07/08/14 10114/14 MEAN

< 0.5

< 0.3

< 0.2

< 0.4

< 0.3

< 0.2 1281 +/- 86 1386 +/- 110 1384 +/- 115 1296 +/- 83 1337 +/- 112 1366 +/- 81 1270 +/- 105 1317 +/- 102 1282 +/- 82 1309 +/- 87

<4

<2

<3

<4

<2

<3

<2

<3

<4

<3

<2

<3

< 24

< 14

< 18

< 26

26

13

< 18

26

<4

<2

<3

<4

<5

<2

<4

<4 25C1 01/14/14 04/01/14 07108/14 10/14/14 MEAN D-5

FIGURE D-1 COMPARISON OF MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES SPLIT BETWEEN ENV AND TBE, 2014 10 9

E N V 8.............

--A--TBE 7.......................................................................................................

L A

6..........................................................

2

,..................:./.....

j*

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec MONTH

FIGURE D-2 COMPARISON OF WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM LGS COLLOCATED LOCATIONS 11SI AND 11S2, 2014 50 40-E 30 20 w

10 0

1 4

7 10 13 16 19 22 25 28 31 34 37 40 43 46 49 52 WEEK NO.

Intentionally left blank

APPENDIX E INTER-LABORATORY COMPARISON PROGRAM

Intentionajly left blank

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2014 (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b)

TBE/Analytics Evaluation (d)

March 2014 E10854 E10855 E10857 E10856 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 95.1 91.7 pCi/L 10.9 15.1 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 96.6 112 449 186 250 248 292 230 312 321 53.0 232 100 122 122 135 ill 140 187 98.5 119 491 210 253 268 297 219 323 337 53.9 223 95.3 115 121 135 99.3 147 153 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 E10858 pCi 74.1 76.4 pCi/L 2090 1760 pCi/L 85.9 91.3 pCi/L 13.8 14.5 1.04 0.72 0.98 0.94 0.91 0.89 0.99 0.93 0.98 1.05 0.97 0.95 0.98 1.04 1.05 1.06 1.01 1.00 1.12 0.95 1.22 0.97 1.19 0.94 0.95 0.95 0.90 1.01 0.91 1.03 0.94 0.99 1.04 1.00 0.97 1.03 1.13 1.00 1.06 1.05 0.99 0.95 1.02 1.07 1.00 0.93 A

W A

A A

A W

A A

June 2014 E10913 E10914 E10916 E10915 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 86.5 111 255 147 123 105 155 106 251 218 95.1 215 122 95.1 88.7 115 72.6 193 179 90.9 124 253 162 120 112 156 102 252 224 92.6 190 122 89.8 84.1 116 76.7 189 168 AP Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 pCi 85.6 85.2 pCi/L 1680 1810 E10917 A

E-I

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2014 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

September2014 E10946 E10947 E10949 E10948 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 90.7 96.9 pCi/L 14.0 16.4 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 92.0 117 281 141 186 137 138 162 75.2 286 97.8 212 106 131 85.7 92.8 113 53.2 202 97.6 126 288 158 193 143 142 158 73.0 297 82.1 188 103 126 93.0 92.3 103 47.5 193 AP Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 pCi 83.9 89.8 pCi/L 2010 1720 0.94 0.85 0.94 0.93 0.98 0.89 0.96 0.96 0.97 1.03 1.03 0.96 1.19 1.13 1.03 1.04 0.92 1.01 1.10 1.12 1.05 0.93 1.17 1.12 0.94 0.93 1.09 0.93 1.16 1.02 1.08 1.02 0.90 0.83 0.90 0.94 0.99 0.95 0.98 0.94 0.98 1.05 0.97 0.95 E10950 E10951 Soil December2014 El1078 El 1079 Milk Milk Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 0.208 0.398 0.216 0.398 0.197 0.242 0.238 0.117 0.447 0.186 0.425 0.233 0.365 0.211 0.209 0.233 0.108 0.438 pCi/L 85.7 95.7 pCi/L 12.9 15.6 A

A A

A pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 85.9 205 402 156 194 122 220 183 287 224 95.1 219 406 164 198 130 225 175 297 235 E-2

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2014 (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

December2014 E11081 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 pCi pCi pCi pCi pCi pCi pCi pCi pCi 96.4 171 73.1 99.0 57.5 107 74.2 144 114 102 190 76.9 92.6 60.8 105 81.6 139 110 0.95 0.90 0.95 1.07 0.95 1.02 0.91 1.04 1.04 0.95 0.89 A

A A

El1080 El1082 pCi 93.5 98.2 pCi/L 1760 1970 (a) Teledyne Brown Engineering reported result.

(b) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(c) Ratio of Teledyne Brown Engineering to Analytics results.

(d) Analytics evaluation based on TBE internal QC limits: A = Acceptable, reported result falls within ratio limits of 0.80-1.20.

W-Acceptable with warning, reported result falls within 0. 70-0.80 or 1.20-1.30. N = Not Acceptable, reported result falls outside the ratio limits of < 0. 70 and > 1.30.

E-3

TABLE E-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2014 (PAGE I OF 1)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b)

Limits Evaluation (c)

May 2014 RAD-97 MRAD-20 Water Sr-89 Sr-90 Ba-133 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 Filter Gr-A Water Sr-89 Sr-90 Ba-133 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 Filter Gr-A pCi/L 38.25 pCi/L 24.65 pCi/L 89.1 pCi/L 45.55 pCi/L 91.15 pCi/L 65.10 pCi/L 244 pCi/L 45.65 pCi/L 27.95 pCi/L 23.75 pCi/L 9.61 pCi/L 8435 pCi/filter 28.0 pCi/L 30.4 pCi/L 18.6 pCi/L 46.8 pCi/L 88.0 pCi/L 99.0 pCi/L 92.5 pCi/L 325 pCi/L 29.9 pCi/L 27.5 pCi/L 15.8 pCi/L 5.74 pCi/L 6255 pCi/filter 27.3 36.7 26.5 87.9 44.3 89.1 64.2 235 61.0 33.0 25.7 10.2 8770 27.5 -43.6 19.2-30.9 74.0 - 96.7 35.5 -48.7 80.2-101 57.8-73.1 212-275 31.9 - 75.8 21.4 -40.7 21.3-30.3 7.95-11.8 7610-9650 A

A A

46.0 15.4-71.4 November 2014 RAD-99 31.4 21.8 49.1 89.8 98.8 92.1 310 37.6 27.4 20.3 5.80 6880 22.8-38.1 15.6-25.7 40.3 - 54.5 73.7 - 98.8 88.9-111 82.9-104 279 - 362 19.4-48.1 17.3 -35.3 16.8 -24.4 4.34 -6.96 5940 - 7570 A

A A

N (1)

A A

MRAD-21 36.9 12.4-57.3 A

(1) The Iodine-131 was evaluated as failed with a ratio of 0. 778. No cause could be found for the slighly low activity. TBE would evaluate this as acceptablie with warning. A rerun was not possible due to 1-131 decay. All ERA Iodine-131 evaluations since 2004 have been acceptable. NCR 14-08 (a) Teledyne Brown Engineering reported result.

(b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported resuit falls within the Control Limits and outside of the Warning Limit.

E-4

TABLE E-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING, 2014 (PAGE 1 OF 2)

Identification Reported Known Acceptance Month/Year Number Media Nuclide*

Units Value (a)

Value (b)

Range Evaluation (c)

March 2014 14-MaW30 Water Am-241 Cs-1 34 Cs-137 Co-57 Co-60 H-3*

Mn-54 Ni-63 Pu-238 Pu-239/240 K-40 Sr-90**

U-234/233*

U-238**

Zn-65 Bq/L 0.764 0.720 0.504 - 0.936 Bq/L 20.7 23.1 16.2-300 Bq/L 28.0 28.9 20.2 - 37.6 Bq/L 26.5 27.5 19.3 - 35.8 Bq/L 15.6 16.0 11.2-20.8 Bq/L NR 321 225-417 Bq/L 13.5 13.9 9.7-18.1 Bq/L NR 34.0 23.8 -44.2 Bq/L 0.911 0.828 0.580 - 1.076 Bq/L 0.751 0.676 0.473 - 0.879 Bq/L NR (1)

Bq/L NR 8.51 5.96 - 11.06 Bq/L NR 0.225 0.158 - 0.293 Bq/L NR 1.45 1.02-1.89 Bq/L

-0.201 (1) 14-MaS30 14-RdF30 14-GrF30 14-RdV30 Soil Cs-1 34 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 AP Cs-1 34**

Cs-1 37*

Co-57*

Co-60**

Mn-54**

Sr-90 Zn-65**

AP Gr-A Gr-B Vegetation Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/kg 2.02 (1)

Bq/kg 1300 1238 867-1609 Bq/kg 1069 966 676-1256 Bq/kg 1.32 1.22 (2)

Bq/kg 1510 1430 1001 -1859 Bq/kg 669 622 435 - 809 Bq/kg 4.14 (1)

Bq/kg 763 695 487-904 Bq/sample NR 1.91 1.34-2.48 Bq/sample NR 1.76 1.23 - 2.29 Bq/sample NR (1)

Bq/sample NR 1.39 0.97-1.81 Bq/sample NR (1)

Bq/sample 0.8220 1.18 0.83-1.53 Bq/sample NR (1)

Bq/sample 0.606 1.77 0.53-3.01 Bq/sample 0.7507 0.77 0.39-1.16 Bq/sample 5.96 6.04 4.23 - 7.85 Bq/sample 5.06 4.74 3.32-6.16 Bq/sample 11.8 10.1 7.1-13.1 Bq/sample 7.34 6.93 4.85 - 9.01 Bq/sample 8.95 8.62 6.03 - 11.21 Bq/sample 1.23 1.46 1.02-1.90 Bq/sample 8.91 7.86 5.50 - 10.22 A

A A

N (3)

A N (3)

N (3)

A A

A N (3)

N (3)

A A

A E-5

TABLE E-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING, 2014 (PAGE 2 OF 2)

Identification Reported Known Acceptance Month/Year Number Media Nuclide*

Units Value (a) Value (b)

Range Evaluation (c)

September 2014 14-MaW31 14-MaS31 Water Am-241 Cs-1 34***

Cs-1 37***

Co-57**

Co-60"**

Mn-54***

Ni-63 Pu-238 Pu-239/240 K-40*-*

Zn-65***

Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/kg Bqlkg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg 0.705 NR NR NR NR NR 24.07 0.591 0.0153 NR NR NR NR NR NR NR NR 694 NR 0.88 0.62-1.14 (1) 18.4 12.9-23.9 24.7 17.3-32.1 12.4 8.7-16.1 14.0 9.8-18.2 24.6 17.2 - 32.0 0.618 0.433 - 0.803 0.0048 (2) 161 113-209 10.9 7.6-14.2 Soil Cs-134***

Cs-137**

Co-57***

Co-60**

Mn-54***

K-40***

Sr-90 Zn-65***

622 1116 779 1009 824 858 541 435-809 (1) 781-1451 545-1013 706-1312 577-1071 601-1115 379-703 A

N (4)

A A

A N (4)

N (4)

A N (4)

N (4)

A 14-RdF31 14-GrF31 AP Sr-90 Bq/sample 0.310 0.703 0.492 - 0.914 September 2014 14-RdV31 AP Gr-A Gr-B Vegetation Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/sample 0.153 0.53 0.16-0.90 Bq/sample 0.977 1.06 0.53-1.59 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 7.31 8.93 10.8 6.31 7.76 0.738 7.16 7.38 8.14 9.2 6.11 7.10 0.85 6.42 5.17-9.59 5.70- 10.58 6.4-12.0 4.28 - 7.94 4.97 - 9.23 0.60-1.11 4.49 - 8.35 A

A A

The MAPEP cross check isotope list has been reduced due to duplication of effort or analysis not being performed for clients.

These nuclides are no longer part of the TBE cross check program due to duplication of effort or analysis not being performed for clients. MAPEP evaluates non-reported analyses as failed if they were reported in the previous series.

- - All future gamma cross check samples for these isotopes will be provided by Analytics.

(1) False positive test.

(2) Sensitivity evaluation.

(3) Water, Ni-63 overlooked when reporting, but the result of 32.7 +- 1.69 would have passed the acceptance criteria. NCR 14-04 Water, the non-detected K-40 was overlooked when reporting, but would have passed the false positive test. NCR 14-04 AP, Sr-90 rerun was within the low range of the acceptqance criteria. The original and rerun results were statistically the same. No cause could be identified for the slightly low Sr-90 activity. NCR 14-04 For non reported (NR) analyses, MAPEP evaluates as failed if they were reported in the previous series. NCR 14-04 (4) AP, Sr-90 gravimetric yield was very high at 117%. Could indicate larger than normal amounts of calcium in the AP. A second fuming HNO 3 separation would be required to remove the excess calcium. NCR 14-09 AP, Gr-Alpha was counted on the wrong side. When flipped over and recounted the results were acceptable. NCR 14-09 For non reported (NR) analyses, MAPEP evaluates as failed if they were reported in the previous series. NCR 14-09 (a) Teledyne Brown Engineering reported result.

(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(c) DOE/MAPEP evaluation: A=acceptable, W=acceptable with warning, N=not acceptable.

E-6

TABLE E-4 ERA (a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAMa ENVIRONMENTAL, INC., 2014 (Page 1 of 1)

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance ERW-1384 ERW-1384 ERW-1 385 ERW-1385 ERW-385 ERW-1385 ERW-1385 ERW-1388 ERW-1388 ERW-1391 ERW-1394 ERW-1397 ERW-5382 ERW-5382 ERW-5385 ERW-5385 ERW-5385 ERW-5385 ERW-5385 ERW-5388 ERW-5388 ERW-5392 ERW-5394 ERW-5397 04/07/14 04/07/14 04/07/14 04/07/14 04/07/14 04/07/14 04/07/14 04/07/14 04/07/14 04/07/14 04/07/14 04/07/14 10/06/14 10/06/14 10/06/14 10/06/14 10/06/14 10/06/14 10/06/14 10/06/14 10/06/14 10/06/14 10/06/14 10/06/14 Sr-89 Sr-90 Ba-1 33 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 Uranium H-3 Sr-89 Sr-90 Ba-1 33 Cs-1 34 Cs-1 37 Co-60 Zn-65 Gr. Alpha G. Beta 1-131 Uranium H-3 40.29 +/-

24.08 +/-

78.23 +/-

62.75 +/-

44.97 +/-

88.54 +

249.1 +/-

56.70 +/-

32.10 +/-

25.52 +/-

10.76 +/-

8982 +/-

29.40 +/-

19.19 +/-

43.54 +/-

81.95 +/-

95.76 +/-

90.25 +/-

327.4 +/-

30.88 +/-

20.47 +/-

19.58 +/-

5.51 +/-

6876 +/-

5.76 2.35 3.93 3.53 3.99 4.93 10.44 2.47 1.20 1.12 0.74 279 36.70 26.50 87.90 64.20 44.30 89.10 235.0 61.00 33.00 25.70 10.20 8770 31.40 21.80 49.10 89.80 98.80 92.10 310.00 37.60 27.40 20.30 5.80 6880 27.50 19.20 74.00 57.80 35.50 80.20 212.0 31.90 21.40 21.30 7.95 7610 22.80 15.60 40.30 73.70 88.90 82.90 279.0 19.40 17.30 16.80 4.34 5940 43.60 30.90 96.70 73.10 48.70 101.00 275.0 75.80 40.70 30.30 11.80 9650 38.10 25.70 54.50 98.80 111.00 104.00 362.0 46.10 35.30 24.40 6.96 7570 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 5.32 1.85 4.54 7.49 5.50 2.77 23.3 8.05 4.75 2.35 0.37 383 a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

b Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.

c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.

E-7

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

ENVIRONMENTAL, INC., 2014 (Page I of 2)

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAW-1140 02/01/14 Gr. Alpha MAW-1140 02/01/14 Gr. Beta 0.77 +/- 0.06 4.31 +/- 0.08 0.85 4.19 0.26 - 1.44 2.10 - 6.29 MAW-1184 MAW-I 184 MAW-1184 MAW-1184 MAW-i 184 MAW-1184 MAW-i 184 MAW-I 184 MAW-1 184 MAW-i 184 MAW-1 184 MAW-1184 MAW-1184 MAW-1184 MAW-1184 MAVE-i 148 MAVE-i 148 MAVE-i 148 MAVE-1 148 MAVE-1 148 MAVE-i 148 MAAP-1151 MAAP-1151 MAAP-1151 MAAP-1151 MAAP-1151 MAAP-1151 MAAP-1 151 MAAP-1 154 MAAP-1 154 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 Fe-55 H-3 Ni-63 Pu-238 Pu-239/240 Sr-90 U-233/234 U-238 Co-57 Co-60 Cs-134 Cs-137 K-40 Mn-54 Zn-65 0.40 345.10 32.40 1.28 0.91 7.00 0.20 1.25 27.86 15.99 21.85 28.74 1.80 14.06 0.00 11.63 7.28 6.29 5.18 9.22 8.59 1.60 1.38 1.75 1.81 0.01

-0.24 1.11

+

+/-

+

3.20 10.60 3.20 0.12 0.10 0.70 0.07 0.18 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Zn-65 Sr-90

+/- 0.38

+/- 0.27

+/- 0.54

+/- 0.49

+/- 2.00

+/- 0.40

+/- 0.19

+/- 0.18

+/- 0.29

+/- 0.20

+/- 0.26

+/- 0.40

+/- 0.05

+/- 0.08

+/- 0.11

+/- 0.10

+/- 0.03

+/- 0.09

+/- 0.14 0.00 321.00 34.00 0.83 0.68 8.51 0.23 1.45 27.50 16.00 23.10 28.90 0.00 13.90 0.00 10.10 6.93 6.04 4.74 8.62 7.86

-0.01 225.00 23.80 0.58 0.47 5.96 0.16 1.02 19.30 11.20 16.20 20.20 0.00 9.70

-0.01

- 2.00

- 417.00

- 44.20

- 1.08

- 0.88

- 11.06

- 0.29

- 1.89

- 35.80

- 20.80

- 30.00

- 37.60

- 10.00

- 18.10

- 0.00

- 13.10

- 9.01

- 7.85

- 6.16

- 11.21

- 10.22 7.10 4.85 4.23 3.32 6.03 5.50 Pass Pass Pass Pass Pass Fail (1)

Fail (1)

Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail (2)

Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail (4)

Pass Pass Pass Pass Pass 0.00 1.39 1.91 1.76 0.00 0.00 1.18 NA 0.97 - 1.81 1.34 - 2.48 1.23 - 2.29 NA

-0.50 - 1.00 0.83 - 1.53 Gr. Alpha Gr. Beta Ni-63 Co-57 Co-60 Cs-1 34 Cs-1 37 K-40 Mn-54 Zn-65 Sr-90 0.56 +/- 0.06 0.98 +/- 0.06 4.80 1064.50 1.70

+/- 15.30

+/- 3.60

+/- 0.50 6.10 +/- 1.80 1364.30 +/- 5.30 728.90 +/- 15.90 1588.00 +/- 6.00 763.50 +/- 6.80 1.23 +/- 1.37 1.77 0.77 0.00 966.00 1.22 0.00 1238.00 622.00 1430.00 695.00 0.00 0.53 -. 3.01 0.39 - 1.16 NA 676.00 - 1256.00 (3)

NA 867.00 - 1609.00 435.00 - 809.00 1001.00 - 1859.00 487.00 - 904.00 NA E-8

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

ENVIRONMENTAL, INC., 2014 (Page 2 of 2)

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MASO-4439 08/01/14 Ni-63 771.62 +/- 23.29 980.00 686.00 - 1274.00 Pass MASO-4439 08/01/14 Sr-90 778.34 +/- 17.82 858.00 601.00 - 1115.00 Pass MASO-4439 08/01/14 Cs-1 34 520.60 +/- 7.09 622.00 435.00 - 809.00 Pass MASO-4439 08/01/14 Co-57 1135.00 +/- 7.40 1116.00 781.00 - 1451.00 Pass MASO-4439 08/01/14 Co-60 768.20 +/- 7.70 779.00 545.00 - 1013.00 Pass MASO-4439 08/01/14 Mn-54 1050.70 +/- 12.60 1009.00 706.00 - 1312.00 Pass MASO-4439 08/01/14 Zn-65 407.89 +/- 15.03 541.00 379.00 - 703.00 Pass MAW-4431 08/01/14 Am-241 0.79 +/- 0.08 0.88 0.62 - 1.14 Pass MAW-4431 08/01/14 Cs-137 18.62 +/- 0.54 18.40 12.90 - 23.90 Pass MAW-4431 08/01/14 Co-57 24.85 +/- 0.42 24.70 17.30 - 32.10 Pass MAW-4431 08/01/14 Co-60 12.27 +/- 0.38 12.40 8.70 - 16.10 Pass MAW-4431 08/01/14 H-3 207.20 +/- 10.60 208.00 146.00 - 270.00 Pass MAW-4431 08/01/14 Fe-55 55.10 +/- 14.80 31.50 22.10 - 41.00 Fail (5)

MAW-4431 08/01/14 Mn-54 14.36 +/- 0.53 14.00 9.80 - 18.20 Pass MAW-4431 08/01/14 Zn-65 11.46 +/- 0.78 10.90 7.60 - 14.20 Pass MAW-4493 08/01/14 Gr. Alpha 0.93 +/- 0.07 1.40 0.42 - 2.38 Pass MAW-4493 08/01/14 Gr. Beta 6.31 +/- 1.35 6.50 3.25 - 9.75 Pass MAAP-4433 08/01/14 Sr-90 0.74 +/- 0.10 0.70 0.49 - 0.91 Pass MAAP-4444 08/01/14 Sr-89 7.82 +/- 0.52 9.40 6.60 - 12.20 Pass MAAP-4444 08/01/14 Sr-90 0.76 +/- 0.10 0.76 0.53-- 0.99 Pass MAVE-4436 08/01/14 Cs-1 34 7.49 +/- 0.18 7.38 5.17 - 9.59 Pass MAVE-4436 08/01/14 Co-57 11.20 +/- 0.19 9.20 6.40 - 12.00 Pass MAVE-4436 08/01/14 Co-60 6.84 +/- 0.17 6.11 4.28 - 7.94 Pass MAVE-4436 08/01/14 Mn-54 8.11 +/- 0.26 7.11 4.97 - 9.23 Pass MAVE-4436 08/01/14 Zn-65 7.76 +/- 0.43 6.42 4.49 - 8.35 Pass 0 Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation).

c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.

(1) The high bias on the plutonium crosscheck samples was traced to contamination from a newly purchased standard.

The results of reanalysis with replacement tracer purchased from NIST:

MAW-1184 Pu-238 0.68 +/- 0.10 Bq I L MAW-1184 Pu-239/240 0.66 +/- 0.10 Bq / L (2) Interference from Eu-152 resulted in misidentification of Co-57.

(3) Provided in the series for "sensitivity evaluation". MAPEP does not provide control limits.

(4) False positive test. Long sample counting time lead to interference from naturally occuring Bi-214 in sample matrix with a close spectral energy.

(5) Result of reanalysis Fe-55 32.63 +/- 16.30 Bq/L E-9

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APPENDIX F ERRATA DATA

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Correction to 2013 AREOR Dosimetry data was documented as a gross value in the 2013 AREOR. Re-evaluation of the data was performed, subtracting out extraneous dose. Extraneous dose is the dose accumulated on a dosimeter prior to and after field deployment from radiation other than that at the field monitoring location. The extraneous dose can include natural terrestrial background radiation, cosmic sources, elevated dose from transport at high altitudes, any manmade sources potentially encountered in transit or at the facility, such as shipments of medical or other radioisotopes or facility sources. The extraneous dose is subtracted from the field dosimeter reading in order to determine the field dose. The subtraction of extraneous dose (also referred to as transit dose) is recommended by ANSI N545-1975, which is supported by the Regulatory Guide 4.13 Revision 1 (July 1977). This change impacts three sections of the 2013 report, as listed below.

Section 3, Program Description F, Radiological Impact to Man and Compliance to 40 CFR 190 Limits, specifically the 1 OCFR1 90 compliance table, was revised to reflect the correct net direct radiation values.

Section 4, Results and Discussion C, Ambient Gamma Radiation was revised to reflect the correct range in dosimeter measurements.

Section 4, Results and Discussion E, Independent Spent Fuel Storage Installation was revised to reflect the correct net direct radiation value.

Additionally, the dosimetry data documented in the 2012 AREOR has also been re-evaluated, subtracting out extraneous dose. The revised data can be found in this Appendix.

F-I

Ill. Program Description F.

Compliance to 40CFR190 Limits A.

Dose to Members of the Public at or Beyond Site Boundary Per ODCM Control 6.2, the Annual Radioactive Effluent Release Report shall include an assessment of the radiation doses to the hypothetically highest exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources. The ODCM does not require population doses to be calculated. For purposes of this calculation the following assumptions were made:

0 Long term annual average meteorology X/Q and D/Q and actual gaseous effluent releases were used.

Gamma air dose, Beta air dose, Total Body and Skin doses were attributed to noble gas releases.

0 Critical organ and age group dose attributed to iodine, particulate, carbon-14 and tritium releases.

100 percent occupancy factor was assumed.

Dosimetry measurements (minus background levels) obtained from the Radiological Environmental Monitoring Program for the nearest residence to the Independent Spent Fuel Storage Installation (ISFSI) was used to determine direct radiation exposure.

The highest doses from the critical organ and critical age group for each release pathway was summed and added to the net dosimetry measurement from nearest residence to the ISFSI for 40CFR190 compliance.

40 CFR 190 Compliance:

The maximum calculated dose to a real individual would not exceed 1.07E+01 mrem (total body), 1.20E+01 mrem (organ), or 1.07 E+01 mrem (thyroid).

All doses calculated were below all ODCM and 40 CFR Part 190 limits to a real individual.

F-2

Table 1 40CFR190 Compliance 40 CFR 190 Compliance Gaseous Effluents Noble Particulate, Liquid Net Direct

% of Total Applicable Limit Unit Gas lodone, C-14 Effluents Radiation Limit

& Tritium Total Body 6.76E-03 3.12E-01 1.79E-04 0.OOE+00 3.19E-01 1.28E+00%

25 mrem Dose Organ Dose 6.76E-031 1.55E+00 I 1.79E-04 0.00E+00 I 1.56E+00 6.23E+00%

25 mrem Thryoid Dose 6.76E-03 3.12E-01 1.78E-04 0.00E+00 3.19E-01 4.25E-01%

75 mrem IV. Results and Discussion C.

Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing A120 3:C optically stimulated luminescence dosimeters. Forty dosimeter locations were established around the site. Results of dosimeter measurements are listed in Appendix C, Tables C-IX.1 and C-IX.2.

Dosimeter measurements were reported in mrem/standard month. Most dosimeter measurements were below 10 mrem/standard month, with a range of 3.8 to 10.3 mrem/month. A comparison of the Site Boundary and Intermediate Distance data to the Control Location (5H1) data indicate that the ambient gamma radiation levels from the Control Location were consistently higher than all other locations, except 13S2. Location 13S2 historically shows higher ambient gamma radiation, which is due to the rock substrate. The area that this dosimeter is located in has been determined to emanate radon prodigy.

E.

Independent Spent Fuel Storage Installation The result of the ambient gamma radiation level at dosimeter location 36S2 was used to determine the direct radiation exposure to the nearest residence from the ISFSI pad. The data, after subtracting background, shows the net direct radiation exposure to the nearest residence was 0.00 mrem for the year.

F-3

Table C-IX.1 QUARTERLY DLR RESULTS FOR LIMERICK GENERATING STATION, 2012 RESULTS IN UNITS OF MILLIROENTGEN/QUARTER +/- 2 STANDARD DEVIATIONS STATION CODE 10E1 1 0F3 10S3 1iSi 13C1 13E1 13S2 14S1 15D1 16F1 17B1 18S2 19D1 20D1 20F1 21S2 23S2 24D1 25D1 25S2 26S3 28D2 29E1 29S1 2E1 31 D1 31 D2 31S1 34E1 34S2 36D1 36S2 3S1 4E1 5H1 5S1 6C1 7E1 7S1 9Cl MEAN

+/-2 S.D.

JAN - MAR APR - JUN JUL - SEP OCT - DEC 6.3 +/- 1.0 6.1 +0.7 6.3 +/- 0.8 7.8 + 0.7 4.1 +/- 0.2 6.2 + 0.9 10.0 + 1.0 5.5 + 0.9 6.9 + 1.0 6.5 + 1.1 5.9 + 0.5 7.3 + 0.9 5.6 + 0.8 5.6 + 0.7 6.0 + 0.3 5.9 +/- 0.8 5.7 + 0.8 5.0 +/- 0.6 4.8 + 0.6 5.2 +/- 0.8 5.6 + 1.3 5.6 + 0.7 5.9 +/- 0.7 5.5 + 0.8 6.9 + 1.3 7.8 +/- 0.7 6.7 +/- 0.9 6.4 +/- 0.7 6.1 +/- 1.0 6.4 + 0.7 5.6 + 0.6 6.4 +/- 1.2 6.1 +/- 0.7 4.6 +/- 0.4 8.1 +1.4 7.1 +/- 0.6 6.5 +/- 1.1 6.5 + 1.0 6.4 + 0.5 6.2 + 1.1 5.5 6.1 6.0 7.6 4.1 5.9 10.6 5.0 6.7 5.8 5.6 7.2 5.1 5.3 5.8 5.6 5.2 4.6 4.6 4.9 5.2 5.3 5.8 5.6 6.7 7.5 7.1 6.0 5.7 6.1 5.3 5.9 5.6 4.4 8.1 6.9 6.0 5.9 6.7 5.9 6.5 6.3 6.5 8.0 4.3 5.8 10.0 6.0 7.1 7.0 6.1 7.7 6.0 5.8 6.1 6.4 6.2 5.2 4.8 5.4 6.3 5.9 5.8 5.7 6.8 8.0 6.6 6.5 6.7 6.5 5.6 7.2 6.4 4.7 7.7 7.3 7.0 6.7 6.2 7.0 6.7 6.5 6.8 8.2 4.0 6.8 9.8 5.8 7.4 7.0 6.1 7.6 5.9 6.0 6.1 5.9 5.9 5.3 5.2 5.5 6.0 5.8 6.5 5.8 7.9 8.2 6.8 6.7 6.2 6.9 6.0 6.1 6.3 4.8 9.1 7.5 6.9 7.1 6.7 6.3 6.3 5.7 6.0 7.5 4.1 6.1 9.5 5.2 6.2 6.3 5.7 6.7 5.5 5.3 5.9 5.5 5.6 5.0 4.6 4.8 5.0 5.3 5.6 4.9 6.3 7.5 6.1 6.3 5.7 6.2 5.4 6.3 6.1 4.4 7.6 6.9 6.0 6.4 6.2 5.7 F-4

Table C-IX.1 QUARTERLY DLR RESULTS FOR LIMERICK GENERATING STATION, 2013 RESULTS IN UNITS OF MILLIROENTGEN/QUARTER +/-2 STANDARD DEVIATIONS STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT - DEC CODE

+/- 2 S.D.

10E1 6.6 +/- 0.9 6.8 +/- 0.1 6.1 +/- 0.6 7.1 +/- 0.8 6.3 +/- 0.7 10F3 6.1 +/- 1.2 6.2 +/- 0.6 6.0 +/- 1.2 6.9 +/- 0.1 5.4 +/- 2.3 10S3 6.4 +/- 0.9 6.4 +/- 0.7 6.1 +/- 0.8 7.0 +/- 0.4 6.0 +/- 2.1 1iSi 7.7 +/- 1.0 7.7 +/- 0.6 7.4 +/- 2.0 8.4 +/- 1.2 7.4 +/- 0.4 13C1 4.2 +/- 0.7 4.4 +/- 0.1 3.8 +/- 0.5 4.6 +/- 0.1 4.0 +/- 0.6 13E1 6.4 +/- 1.1 6.2 +/- 0.9 6.3 +/- 1.5 7.2 +/- 1.6 5.9 +/- 0.1 13S2 9.7 +/- 1.0 9.8 +/- 0.7 9.1 +/- 2.3 10.3 +/- 1.5 9.4 +/- 1.2 14S1 5.6 +/- 0.7 5.4 +/- 0.5 5.5 +/- 1.5 6.1 +/- 0.2 5.3 +/- 0.9 15D1 6.8 +/- 0.8 6.6 +/- 0.3 6.6 +/- 1.0 7.3 +/- 1.0 6.5 +/- 0.4 16F1 6.6 +/- 0.9 6.5 +/- 0.8 6.5 +/- 0.3 7.2 +/- 0.9 6.1 +/- 0.8 17B1 5.9 +/- 0.6 6.1 +/- 0.6 5.4 +/- 0.2 6.1 +/- 0.2 5.8 +/- 0.6 18S2 7.0 +/- 0.9 7.2 +/- 0.1 6.6 +/- 0.7 7.5 +/- 0.9 6.8 +/- 0.2 19D1 6.3 +/- 1.3 5.8 +/- 1.3 6.5 +/- 2.2 7.1 +/- 1.1 5.7 +/- 0.0 20D1 5.5 +/- 0.9 5.8 +/- 0.1 5.4 +/- 0.6 6.0 +/- 0.1 5.0 +/- 0.4 20F1 6.1 +/- 1.1 5.8 +/- 0.3 6.2 +/- 0.8 6.9 +/- 0.3 5.6 +/- 0.2 21S2 6.0 +/- 1.3 5.8 +/- 0.0 6.0 +/- 1.5 6.9 +/- 1.9 5.5 +/- 1.1 23S2 5.8 +/- 0.9 6.0 +/- 0.1 5.7 +/- 0.3 6.3 +/- 0.3 5.3 +/- 0.3 24D1 5.4 +/- 1.2 5.1 +/- 0.7 5.6 +/- 2.0 6.2 +/- 0.4 4.9 +/- 1.4 25D1 4.8 +/- 0.5 4.8 +/- 0.0 4.6 +/- 1.5 5.2 +/- 0.5 4.8 +/- 1.3 25S2 5.2 +/- 0.8 5.1 +/- 0.8 5.2 +/- 1.1 5.8 +/- 0.1 4.8 +/- 0.5 26S3 5.4 +/- 0.6 5.5 +/- 0.3 5.2 +/- 0.5 5.8 +/- 0.8 5.2 +/- 0.0 28D2 5.5 +/- 0.8 5.5 +/- 0.7 5.4 +/- 0.1 6.1 +/- 0.3 5.1 +/- 1.0 29E1 5.6 +/- 1.5 5.0 +/- 0.1 5.7 +/- 0.3 6.7 +/- 0.1 5.2 +/- 0.1 29S1 5.2 +/- 0.8 5.5 +/- 0.3 5.0 +/- 0.4 5.6 +/- 0.2 4.8 +/- 0.2 2E1 6.6 +/- 1.2 6.2 +/- 0.4 6.5 +/- 1.2 7.5 +/- 1.3 6.3 +/- 0.3 3101 7.9 +/- 1.2 8.2 +/- 0.4 7.5 +/- 1.0 8.6 +/- 0.7 7.4 +/- 1.5 31D2 6.6 +/- 1.4 6.5 +/- 0.7 6.5 +/- 2.9 7.5 +/- 0.7 5.9 +/- 1.5 31S1 6.6 +/- 0.9 6.5 +/- 0.0 6.3 +/- 0.1 7.2 +/- 0.2 6.3 +/- 0.6 34E1 6.0 +/- 0.9 6.1 +/- 0.2 5.5 +/- 2.3 6.5 +/- 0.1 5.7 +/- 0.5 34S2 6.7 +/- 1.5 6.8 +/- 1.5 6.6 +/- 0.7 7.6 +/- 0.6 5.7 +/- 0.1 36D1 5.6 +/- 1.0 5.4 +/- 0.2 5.4 +/- 2.5 6.3 +/- 1.3 5.2 +/- 0.9 36S2 6.5 +/- 1.4 6.5 +/- 0.6 6.4 +/- 0.0 7.4 +/- 0.1 5.6 +/- 1.3 3S1 6.5 +/- 1.4 6.5 +/- 0.4 6.5 +/- 3.1 7.4 +/- 0.3 5.7 +/- 0.9 4E1 4.4 +/- 1.0 4.6 +/- 0.4 4.1 +/- 1.2 4.9 +/- 0.8 3.8 +/- 1.0 5H1 8.3 +/- 1.0 8.3 +/- 0.1 7.9 +/- 0.8 9.0 +/- 2.4 8.0 +/- 2.9 5S1 7.6 +/- 0.9 7.7 +/- 0.1 7.1 +/- 0.2 8.1 +/- 1.4 7.3 +/- 0.6 6C1 6.4 +/- 1.0 6.1 +/- 0.2 6.2 +/- 0.0 7.1 +/- 0.0 6.2 +/- 0.2 7E1 6.7 +/- 1.0 6.5 +/- 1.0 6.5 +/- 0.9 7.5 +/- 2.6 6.4 +/- 0.4 7S1 6.6 +/- 0.8 6.6 +/- 1.1 6.2 +/- 0.1 7.2 +/- 0.2 6.4 +/- 0.5 9C1 6.3 +/- 1.7 6.0 +/- 0.3 6.5 +/- 1.0 7.4 +/- 0.1 5.4 +/- 0.3 F-5

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APPENDIX G ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

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Docket No:

50-352 50-353 LIMERICK GENERATING STATION UNITS 1 and 2 Annual Radiological Groundwater Protection Program Report 1 January Through 31 December 2014 Prepared By Teledyne Brown Engineering Environmental Services Exelon Generation April 2015

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Table of Contents I. Sum m ary and Conclusions..........................................................................................

1 I1. Introduction............................................................................................................

2 A. O bjectives of the RG PP................................................................................

2 B. Im plem entation of the O bjectives..................................................................

2 C. Program Description.......................................................................................

3 D. Characteristics of Tritium (H-3).......................................................................

4 Ill. Program Description.................................................................................................

4 A. Sam ple Analysis.............................................................................................

4 B. Data Interpretation..........................................................................................

5 C. Background Analysis......................................................................................

6

1. Background Concentrations of Tritium...............................................

6 IV. Results and Discussion............................................................................................

8 A. G roundwater Results......................................................................................

8 B. Surface W ater Results...................................................................................

8 C. Precipitation W ater Results............................................................................

9 D. Drinking W ater W ell Survey............................................................................

9 E. Summary of Results - Inter-laboratory Comparison Program......................

10 F. Leaks, Spills, and Releases.........................................................................

10 G. Trends...........................................................................................................

10 H. Investigations..............................................................................................

10 I. Actions Taken.................................................................................................

10 V. References...................................................................................................................

10

Appendices Appendix A Tables Table A-1 Location Designation Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2014 Fi.gures Figure 1 Figure 2 Figure 3 Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2014 Routine Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2014 Routine Precipitation Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2014 Appendix B Tables Table B-1.1 Table B-1.2 Table B-11.1 Table B-11.2 Table B-Ill.1 Data Tables Concentrations of Tritium, Strontium-89, Strontium-90, Gross Alpha and Gross Beta in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2014 Concentrations of Gamma Emitters in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2014 Concentration of Tritium in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2014 Concentrations of Gamma Emitters in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2014 Concentrations of Tritium in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2014.

I.

Summary and Conclusions This report on the Radiological Groundwater Protection Program (RGPP) conducted for the Limerick Generating Station (LGS) by Exelon Nuclear covers the period 01 January 2014 through 31 December 2014. During that time period, 245 analyses were performed on 118 samples from 13 groundwater, 7 surface water and 4 precipitation water locations collected from the environment, both on and off station property in 2014.

Groundwater and surface water was analyzed for tritium. All sample results were at concentrations less than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Low levels of tritium were detected at three of the thirteen groundwater monitoring locations. Low levels of tritium were detected at one of the seven surface water monitoring locations. All other results were less than the required Exelon specified LLD of 200 pCi/L.

Groundwater and surface water was analyzed for Strontium-89 and Strontium-

90. All Sr-89 and Sr-90 results were less than the MDA.

Groundwater and surface water was analyzed for gross alpha and gross beta in dissolved and suspended fractions. Gross alpha (dissolved) was detected at 3 of 13 groundwater locations sampled. Gross alpha (suspended) was detected at 2 of 13 groundwater locations sampled. Gross beta (dissolved) was detected at 12 of 13 groundwater locations sampled. Gross beta (suspended) was detected at 3 of 13 groundwater locations.

Groundwater and surface water was analyzed for gamma emitting radionuclides associated with the renewed licensed plant operation. All gamma isotopic results were less than the MDA.

Precipitation water samples were analyzed for tritium. Tritium was detected at 1 of 4 precipitation locations sampled.

In assessing all the data gathered for this report, it was concluded that the operation of Limerick Generating Station had no adverse radiological impact on the environment offsite of LGS.

1

Introduction The Limerick Generating Station (LGS), consisting of two 3515 MWt boiling water reactors owned and operated by Exelon Corporation, is located adjacent to the Schuylkill River in Montgomery County, Pennsylvania. Unit No. 1 went critical on 22 December 1984. Unit No. 2 went critical on 11 August 1989. The site is located in Piedmont countryside, transversed by numerous valleys containing small tributaries that feed into the Schuylkill River. On the eastern river bank elevation rises from approximately 110 to 300 feet mean sea level (MSL). On the western river bank elevation rises to approximately 50 feet MSL.

This report covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2014.

In 2006, Exelon instituted a comprehensive program to evaluate the impact of station operations on groundwater and surface water in the vicinity of Limerick Generating Station. This evaluation involved numerous station personnel and contractor support personnel.

A.

Objective of the RGPP The long-term objectives of the RGPP are as follows:

1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources.

2. Understand the local hydrogeologic regime in the vicinity of the station and maintain up-to-date knowledge of flow patterns on the surface and shallow subsurface.

3. Perform routine water sampling and radiological analysis of water from selected locations.

4. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner.

5. Regularly assess analytical results to identify adverse trends.

6. Take necessary corrective actions to protect groundwater resources.

B.

Implementation of the Objectives The objectives identified have been implemented at Limerick Generating Station as discussed below:

1.

Exelon and its consultant identified locations as described in the 2006 Phase 1 study. The Phase 1 study results and conclusions were made available to state and federal regulators in station specific reports.

2

2.

The Limerick Generating Station reports describe the local hydrogeologic regime. Periodically, the flow patterns on the surface and shallow subsurface are updated based on ongoing measurements.

3.

Limerick Generating Station will continue to perform routine sampling and radiological analysis of water from selected locations.

4.

Limerick Generating Station has procedures to identify and report new leaks, spills, or other detections with potential radiological significance in a timely manner.

5.

Limerick Generating Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends.

C.

Program Description Samples for the ongoing ground water monitoring program were collected for Exelon Nuclear by Normandeau Associates, Inc. (NAI). This section describes the general collection methods used to obtain environmental samples for the LGS RGPP in 2014. Sample locations can be found in Table A-i, Appendix A.

1.

Sample Collection Groundwater and Surface Water Samples of both groundwater and surface water were collected, managed, transported and analyzed in accordance with approved procedures following EPA methods. Sample locations, sample collection frequencies and analytical frequencies were controlled in accordance with approved station procedures. Contractor and/or station personnel were trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events. Analytical laboratories were subject to internal quality assurance programs, industry cross-check programs, as well as nuclear industry audits. Station personnel reviewed and evaluated all analytical data deliverables as data were received.

Both station personnel and an independent hydrogeologist reviewed analytical data results for adverse trends or changes to hydrogeologic conditions.

Precipitation A five gallon precipitation collection bucket fitted with a funnel was installed a four locations around the Limerick Generating Station.

Three collection buckets were located on site boundary in the highest prevalent wind sectors and one located on site in the least prevalent 3

wind sector.

D.

Characteristics of Tritium (H-3)

Tritium (chemical symbol H-3) is a radioactive isotope of hydrogen. The most common form of tritium is tritium oxide, which is also called "tritiated water."

The chemical properties of tritium are essentially those of ordinary hydrogen.

Tritiated water behaves the same as ordinary water in both the environment and the body. Tritium can be taken into the body by drinking water, breathing air, eating food, or absorption through skin. Once tritium enters the body, it disperses quickly and is uniformly distributed throughout the body. Tritium is excreted primarily through urine with a clearance rate characterized by an effective biological half-life of about 14 days. Within one month or so after ingestion, essentially all tritium is cleared. Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period.

Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production reactors, where the isotopes lithium-7 and/or boron-10 are activated to produce tritium. Like normal water, tritiated water is colorless and odorless. Tritiated water behaves chemically and physically like non-tritiated water in the subsurface, and therefore tritiated water will travel at the same velocity as the average groundwater velocity.

Tritium has a half-life of approximately 12.3 years. It decays spontaneously to helium-3 (3He). This radioactive decay releases a beta particle (low-energy electron). The radioactive decay of tritium is the source of the health risk from exposure to tritium. Tritium is one of the least dangerous radionuclides because it emits very weak radiation and leaves the body relatively quickly.

Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue.

Ill.

Program Description A.

Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the Limerick Generating Station RGPP in 2014.

In order to achieve the stated objectives, the current program includes the following analyses:

1.

Concentrations of tritium in groundwater, surface water and precipitation water.

4

2.

Concentrations of Gross Alpha, Dissolved and Suspended and Gross Beta, Dissolved and Suspended in groundwater.

3.

Concentrations of gamma emitters (Be-7, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, 1-131, Cs-134, Cs-137, Ba-140, and La-140) in groundwater and surface water.

4.

Concentrations of strontium (Sr-89 and Sr-90) in groundwater and surface water.

B.

Data Interpretation The radiological data collected prior to Limerick Generating Station becoming operational were used as a baseline with which these operational data were compared. For the purpose of this report, Limerick Generating Station was considered operational at initial criticality. Several factors were important in the interpretation of the data:

1.

Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) is defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5%

probability of falsely concluding that a blank observation represents a "real" signal. The LLD is intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criterion for the presence of activity. All analyses were designed to achieve the required LGS detection capabilities for environmental sample analysis.

The minimum detectable concentration (MDC) is defined above with the exception that the measurement is an after the fact estimate of the presence of activity.

2.

Laboratory Measurements Uncertainty The estimated uncertainty in measurement of tritium in environmental samples is frequently on the order of 50% of the measurement value.

Statistically, the exact value of a measurement is expressed as a range with a stated level of confidence. The convention is to report results with a 95% level of confidence. The uncertainty comes from calibration standards, sample volume or weight measurements, sampling uncertainty and other factors. Exelon reports the uncertainty of a measurement created by statistical process (counting error) as well as all sources of error (Total Propagated Uncertainty or TPU).

Each result has two values calculated. Exelon reports the TPU by following the result with plus or minus (+/-) the estimated sample standard deviation, as TPU, that is obtained by propagating all sources of analytical uncertainty in measurements.

5

Analytical uncertainties are reported at the 95% confidence level in this report for reporting consistency with the AREOR.

C.

Background Analysis A pre-operational radiological environmental monitoring program (pre-operational REMP) was conducted to establish background radioactivity levels prior to operation of the Station. The environmental media sampled and analyzed during the pre-operational REMP were atmospheric radiation, fall-out, domestic water, surface water, aquatic life, and foodstuffs. The results of the monitoring were detailed in the report entitled, Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2, 1 January 1982 through 21 December 1984, Teledyne Isotopes and Radiation Management Corporation.

The pre-operational REMP contained analytical results from samples collected from both surface water and groundwater.

Monthly surface water sampling began in 1982, and the samples were analyzed for tritium as well as other radioactive analytes. During the preoperational program tritium was detected at a maximum concentration of 420 pCi/L, indicating that these preoperational results were from nuclear weapons testing and is radioactively decaying as predicted. Gamma isotopic results from the preoperational program were all less than or at the minimum detectable concentration (MDC) level.

1.

Background Concentrations of Tritium The purpose of the following discussion is to summarize background measurements of tritium in various media performed by others.

Additional detail may be found by consulting references.

a.

Tritium Production Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper atmosphere, "Cosmogenic" tritium is produced from the bombardment of stable nuclides and combines with oxygen to form tritiated water, which will then enter the hydrologic cycle.

Below ground, "lithogenic" tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.

A major anthropogenic source of tritium and strontium-90 6

comes from the former atmospheric testing of thermonuclear weapons. Levels of tritium in precipitation increased significantly during the 1950s and early 1960s, and later with additional testing, resulting in the release of significant amounts of tritium to the atmosphere. The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment.

b.

Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides.

Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in Precipitation (GNIP) and USEPA's RadNet database. GNIP provides tritium precipitation concentration data for samples collected worldwide since 1960. RadNet provides tritium precipitation concentration data for samples collected at stations throughout the U.S. Based on GNIP data for sample stations located in the U.S. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermonuclear weapons. Tritium concentrations in surface water showed a sharp decline up until 1975 followed by a gradual decline since that time. Tritium concentrations have typically been below 100 pCi/L since approximately 1980.

Tritium concentrations in wells may still be above the 200 pCi/L detection limit from the external causes described above.

Water from previous years was naturally captured in groundwater. As a result, some well water sources today are affected by the surface water from the 1960s that contained elevated tritium activity.

c.

Surface Water Data Tritium concentrations are routinely measured in the Schuylkill and Delaware Rivers. Pennsylvania surface water data are typically less than 100 pCi/L.

The USEPA RadNet surface water data typically has a reported

'Combined Standard Uncertainty' of 35 to 50 pCi/L. According to USEPA, this corresponds to a +/-70 to 100 pCi/L 95%

confidence bound on each given measurement. Therefore, the typical background data provided may be subject to measurement uncertainty of approximately +/- 70 to 100 pCi/L.

The radioanalytical laboratory is counting tritium results to an Exelon specified LLD of 200 pCi/L. Typically, the lowest 7

positive measurement will be reported within a range of 40 -

240 pCi/L or 140 +/- 100 pCi/L. Clearly, these sample results cannot be distinguished as different from background at this concentration.

IV.

Results and Discussion A.

Groundwater Results Samples were collected from onsite wells throughout the year in accordance with the station Radiological Groundwater Protection Program. Analytical results and anomalies are discussed below.

Tritium Samples from thirteen locations were analyzed for tritium activity (Appendix B, Table B-I.11). Tritium values ranged from non-detectable to 613 pCi/L.

Although no drinking water pathway is available from groundwater, the theoretical dose via the drinking water pathway was calculated at 3.63E-02 mrem to a child (total body), which represents 0.60% of the 10 CFR 50, Appendix I dose limit of 6 mrem.

Strontium Samples were analyzed for Sr-89 or Sr-90. All results were below the required LLDs (Appendix B, Table B-1.1).

Gross Alpha and Gross Beta (dissolved and suspended)

All samples were analyzed for gross alpha and gross beta in the dissolved and suspended fractions during all quarters in 2014. Gross alpha (dissolved) was detected in 3 of 13 groundwater locations sampled. The concentrations ranged from 0.9 to 1.3 pCi/L. Gross alpha (suspended) was detected in 2 of 13 groundwater locations sampled. The concentrations ranged from 1.8 to 3.7 pCi/L. Gross beta (dissolved) was detected in 12 of 13 groundwater locations sampled. The concentrations ranged from 2.6 to 16.8 pCi/L. Gross beta (suspended) was detected in 3 of 13 groundwater locations sampled.

The concentrations ranged from 2.1 to 6.7 pCi/L (Appendix B, Table B-I.1).

Gamma Emitters Samples were analyzed for gamma emitting nuclides. All results were below the required LLDs (Appendix B, Table B-1.2).

B.

Surface Water Results In accordance with the Station's Radiological Groundwater Protection Program surface water samples were collected from streams that transverses the site, as well as, from other water bodies that could influence the tritium 8

concentration at Limerick. Analytical results and anomalies are discussed below.

Tritium Samples from seven locations were analyzed for tritium activity (Appendix B, Table B-11.1). Tritium values ranged from non-detectable to 262 pCi/L. The theoretical dose via the drinking water pathway was calculated at 1.55E-02 mrem to a child (total body), which represents 0.26% of the 10 CFR 50, Appendix I dose limit of 6 mrem.

Strontium Sr-89 and Sr-90 were not analyzed in 2014.

Gamma Emitters No gamma emitting nuclides were detected in any surface water samples analyzed (Appendix B, Table B-11.2).

C.

Precipitation Sample Results Tritium Tritium activity was detected in one of four precipitation water locations analyzed at a concentration of 444 pCi/L. This concentration is consistent with historical values observed. (Appendix B, Table B-Ill.1).

D.

Drinking Water Well Survey A drinking water well survey was conducted during the summer 2006 by CRA (CRA 2006) around the Limerick Generating Station. CRA reviewed the Pennsylvania Groundwater Information System database to identify wells within a 1-mile radius from the center of the Station. Forty-six domestic withdrawal wells, two industrial wells, two commercial wells, and one institutional well were identified within the specified radius. The well depths range from 78 to 345 feet below ground surface (bgs), and they yield between 8 and 100 gallons per minute (gpm). All wells are completed in the Brunswick Formation.

The Station has one potable supply well and one fire water well. The potable supply well is constructed as an open-rock borehole. Groundwater was measured at a depth 102 feet bgs during a well pump replacement in 2014.

The pump was placed at a depth of approximately 294 feet bgs. The total well depth and the depth of the steel casing are approximately 310 feet bgs.

The well is located approximately 175 feet east of the Reactor Building. The fire water well is constructed as an open-rock borehole. Groundwater was encountered at 121 feet bgs during a well pump replacement in 2004. The well pump was placed at a depth of approximately 399 feet bgs. The total well depth and the depth of the steel casing are unknown. The well is located 9

approximately 500 feet east of the cooling towers. The well is used only in an emergency fire situation; therefore, water use is estimated to be zero.

E.

Summary of Results - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE are presented in the Annual Radiological Environmental Operating Report.

F.

Leaks, Spills, and Releases There were no spills to ground containing radioactive material in 2014.

However, during the first quarter of 2014, tritiated water was identified leaking from the expansion joints of the Unit 1 Turbine Building condenser bay. The water was contained and disposed of via the normal radioactive waste processing system. No elevated tritium results were observed in the monitoring wells.

G.

Trends No trends were identified.

H.

Investigations Currently no investigations are ongoing. Conclusions from the Phase 1 report have been made available to state and federal regulators and to the public.

1.

Actions Taken

1. Compensatory Actions There have been no station events requiring compensatory actions at the Limerick Generating Station.

2. Installation of Monitoring Wells No new wells were installed in 2014.

3. Actions to Recover/Reverse Plumes No actions were required to recover or reverse groundwater plumes.

V.

References

1. Conestoga Rovers and Associates, Fleetwide Assessment, Limerick Generating Station, Sanatoga, Pennsylvania, Ref. No. 045136(17), September 2006

2. Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2, 1 January 1982 through 21 December 1984, Teledyne Isotopes and Radiation Management Corporation 10

APPENDIX A LOCATION DESIGNATION

Intentionally left blank

TABLE A-1:

Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2014 Location MW-LR-1 MW-LR-2 MW-LR-3 MW-LR-4 MW-LR-5 MW-LR-6 MW-LR-7 MW-LR-8 MW-LR-9 P11 P14 P16 P17 P3 SP22 DW-LR-1 Type Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Distance Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite SW-LR-2 SW-LR-4 SW-LR-6 SW-LR-7 SW-LR-8 (Hold Pond)

SW-LR-9 (Spray Pond)

SW-LR-10 Surface Water Surface Water Surface Water Surface Water Surface Water Surface Water Surface Water Offsite Offsite Offsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite 36S3 E-5 ESE-6 SE-7 Precipitation Water Precipitation Water Precipitation Water Precipitation Water A-I

Figure 1 Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2014.

A-2

0 SW-LR-3 Figure 2 Routine Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2014.

A-3

m M a 0MOOWOM P~

uLseab Figure 3 Routine Precipitation Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2014.

A-4

APPENDIX B DATA TABLES

Intentionally left blank

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis)

Gr-A (Sus)

Gr-B (Dis)

Gr-B (Sus)

LW-LR-1 DW-LR-1 DW-LR-1 DW-LR-1 MW-LR-1 MW-LR-2 MW-LR-2 MW-LR-2 MW-LR-2 MW-LR-3 MW-LR-3 MW-LR-3 MW-LR-3 MW-LR-4 MW-LR-4 MW-LR-4 MW-LR-4 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-7 MW-LR-7 MW-LR-7 MW-LR-7 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 P-11 02/06/14 05/08/14 08/05/14 11/04/14 05/06/14 02/04/14 05/07/14 08/05/14 11/04/14 02/04/14 05/06/14 08/06/14 11/05/14 02/04/14 05/07/14 08/05/14 11/04/14 02/04/14 05/07/14 05/07/14 05/07/14 08/05/14 11/04/14 02/04114 05/06/14 08/06/14 11/05/14 02/06/14 02/06/14 05/06/14 05/06/14 05/06/14 08/05/14 08/05/14 08/05/14 11/04/14 11104/14 11/04/14 02/06/14 02/06/14 02/25/14 03/12/14 03/12/14 04/25/14 05/06/14 05/06/14 05/06/14 08/05/14 08/05/14 08/05/14 11/04/14 11/04/14 11/04/14 02/06/14

< 155

< 189

< 182

< 183

< 192

< 180

<184

< 180

< 160

< 155

< 184

< 181

< 160

< 158

< 184

< 183

< 160

< 152 TBE

< 190 TBE 348 +/- 135 EIML 251 +/- 83

< 178 202 +/- 113

< 184

< 180

< 185

< 183 368 +/- 116 205 +/- 108 TBE 271 +/- 132 TBE 277 +/- 132 EIML 249 +/- 82 TBE 229 +/- 127 TBE 229 +/- 126 EIML 207 +/- 83 TBE 233 +/- 119 TBE 284 +/- 119 EIML < 179 553 +/- 126 506 +/- 128 453 +/- 140 TBE 562 +/- 132 EIML 613 +/- 101 362 +/- 138 TBE 343 +/- 138 TBE 441 +/- 142 EIML 325 +/- 86 TBE 249 +/- 109 TBE 226 +/- 109 EIML 191 +/- 83 TBE 302 +/- 126 TBE 252 +/- 115 EIML 292 +/- 124

< 185

< 5.2

< 0.7 1.1 +/- 0.7 < 0.9

< 0.9

< 3.7

< 4.7

< 4.2

< 4.6

< 6.0

< 0.8

< 6.2

< 4.7

< 5.9

< 0.3

< 4.6

< 4.3

< 0.9

< 0.6 0.9 +/- 0.5 1.8 +/- 0.9

<0.6

<1.5

<0.4

<3.5

< 0.5

< 0.6

< 0.9

< 1.1

< 0.8

< 0.9

< 0.8

< 0.9

< 0.8 3.0 +/- 1.0

< 1.6 5.2 +/- 1.1

< 1.6 2.6 +/- 0.8 2.1 +/-1.1 4.4 +/- 1.2

< 1.5 6.1 +/- 1.5

< 1.5 5.4 +/- 1.1

< 1.6 8.1 +/- 1.3

< 1.5 3.3 +/- 0.8

< 1.5 5.2 +/- 1.5

< 1.6 2.9 +/- 1.4

< 1.5 7.3 +/- 1.2

< 1.6 5.5 +/- 1.2

< 1.5

< 0.6

< 0.7

< 0.5

< 0.7

< 0.5

< 0.6

< 2.5

< 3.5 1.3 +/- 0.8 < 0.9

< 1.1

< 0.9 B-I

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis)

Gr-A (Sus)

Gr-B (Dis)

Gr-B (Sus)

P-11 P-11 P-11 P-14 P-14 P-14 P-14 P-16 P-16 P-17 05/07/14 08/05/14 11/04/14 02/06/14 05/07/14 08/05/14 11/04/14 05/06/14 12/30/14 05/06/14

< 187

< 182

< 170

< 156

< 194

< 180

< 170

< 190

< 179

< 185

< 5.2

< 4.5

< 5.1

<0.7

<4.4

<0.7

<3.5

<0.5

<3.5

< 2.3

< 0.8

< 1.1 16.8 +/- 1.9

< 1.5 2.6 +/- 1.4 6.7 +/- 1.5 3.7 +/- 1.2 12.2 +/- 4.3 2.8 +/- 1.2

< 0.9 5.1 +/- 1.5

< 1.6 B-2

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 DATE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 DW-LR-1 05/08/14

< 60 MW-LR-1 05/06/14

< 64 MW-LR-2 05/07/14

< 42 MW-LR-3 05/06/14

< 55 MW-LR-4 05/07/14

< 34 MW-LR-5 05/07/14 TBE

< 60 MW-LR-5 05/07/14 TBE

< 69 MW-LR-5 05/07/14 EIML < 32 MW-LR-7 05/06/14

< 45 MW-LR-8 05/06/14 TBE

< 53 MW-LR-8 05/06/14 TBE

< 47 MW-LR-8 05/06/14 EIML < 23 MW-LR-9 05/06/14 TBE

< 47 MW-LR-9 05/06/14 TBE

< 59 MW-LR-9 05/06/14 EIML < 19 P-11 05/07/14

< 55 P-14 05/07/14

< 44 P-16 05/06/14

< 60 P-17 05/06/14

< 65

< 94

< 66

< 40

46

< 88

< 47

< 81

< 70

< 49

< 85

116

56

70

< 95

60

130

< 96

70

< 79

<6

<7

<4

<6

<5

<4

<6

<7

<8

<3

<2

<4

<5

<6

<2

<3

<4

<5

<6

<3

<2

<5

<7

<4

<5

<8

<6

<7

<13

14

<9

< 16

17

<8

<9

10

15

<5

<15

<10

<7

< 14

<9

<17

14

<5

<15

<7

<15

<9

<5

<11

<6

<11

<6

<4

<9

<5

<7

<17

<8

<7

<16

<9

<5

<9

<6

<4

<9

<6

<10

<7

<6

<12

<5

<2

<5

<4

<5

<9

<6

<5

<12

<7

<2

<6

<2

<7

<15

<6

<5

<10

<6

<16

<7

<15

<8

12

<14

<7

<9

<8

<11

< 14

<6

<10

<9

<12

<4

<11

< 10

<5

< 14

<9

14

12

<11

<6

<8

<28

< 12

<6

<7

<31

<8

<5

<4

<20

<9

<6

<5

<25

<7

<4

<20

<11

<7

<8

<33

< 12

< 7

< 31

<8

<5

<3

<13

<10

<5

<23

< 10

<4

<6

<26

<12

<5

<6

<29

<6

<3

<2

<14

<11

<5

<25

<12

<7

<33

<7

<3

<18

< 12

<7

<6

<30

<9

<5

<6

<27

<13

<7

<8

<34

<13

<6

<8

<33

<9

< 10

<7

<6

<9

< 12

<5

<8

<9

<11

<4

<8

< 10

<3

< 11

<9

< 12

< 11

TABLE B-11.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE SW-LR-10 SW-LR-10 SW-LR-10 SW-LR-10 SW-LR-2 SW-LR-2 SW-LR-2 SW-LR-2 SW-LR-4 SW-LR-4 SW-LR-4 SW-LR-4 SW-LR-6 SW-LR-6 SW-LR-6 SW-LR-6 SW-LR-7 SW-LR-7 SW-LR-7 SW-LR-7 SW-LR-8 SW-LR-8 SW-LR-8 SW-LR-8 SW-LR-8 SW-LR-8 SW-LR-8 SW-LR-8 SW-LR-9 SW-LR-9 SW-LR-9 SW-LR-9 COLLECTION DATE 02/07114 05/05/14 08104114 11/03/14 02/07/14 05/05/14 08104114 11103/14 02/07/14 05/05/14 08/04/14 11/03/14 02/07/14 05/05/14 08104/14 11/03/14 02/07/14 05/05/14 08104114 11/03/14 02/04/14 05/07/14 Oni 05/07/14 Re 05/07/14 Re; 08/05/14 TBI 08/05/14 TBI 08/05/14 EIN 11/04/14 02/04/14 05/05/14 08/04/14 11/04/14 H-3

149

188

181

175

155

196

<184

173

<154

193

181

174

154

195

181

172

156

<194

182

175

154 252 +/- 134 231 +/- 118 262 +/- 132

182

180

144

195 ginaI count analysis E

E

< 153

< 193

< 181

< 179 B-4

TABLE B-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 DATE SW-LR-10 05/05/14

< 63 SW-LR-2 05/05/14

< 45 SW-LR-4 05/05/14

< 37 SW-LR-6 05/05/14

< 42 SW-LR-7 05/05/14

< 41 SW-LR-8 05/07/14

< 61 SW-LR-9 05/05/14

< 48 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140

<. II

< 39

<54

< 35

107

163

112

<5

<4

<6

<7

<5

<6

<4

<7

<8

<5

< If f

<10

<5

<12

<6

<10

<4

<8

<5

<13

<8

<10

<5

<. eu

<8

< 10

<6

<11

< 14

<6

<5

<6

<5

<6

<8

<9

<8

<11

12

10 HO 11 10 10 12 12 10

<5

<4

<6

<5 IU

<5

<4

<9

<5

25

29

22

28

30

< 32

<7

< 12

<8

< 12

<8

<7

TABLE B-Ill.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE 36S3 36S3 36S3 36S3 36S3 36S3 36S3 36S3 36S3 36S3 36S3 E-5 E-5 E-5 E-5 E-5 E-5 E-5 E-5 E-5 E-5 E-5 E-5 ESE-6 ESE-6 ESE-6 ESE-6 ESE-6 ESE-6 ESE-6 ESE-6 ESE-6 ESE-6 ESE-6 ESE-6 SE-7 SE-7 SE-7 SE-7 SE-7 SE-7 SE-7 SE-7 SE-7 SE-7 SE-7 SE-7 COLLECTION DATE 12/23/13 01/27114 02/25/14 03/31/14 04/25/14 05/27/14 06/27/14 07/29/14 08/27/14 09/26/14 10/28/14 12/23/13 01/27/14 02/25/14 03/31/14 04/25/14 05/27/14 06/27/14 07/29/14 08/27/14 09/26/14 10/28/14 11/24/14 12/23/13 01/27/14 02/25/14 03/31/14 04/25/14 05/27/14 06/27/14 07/29/14 08/27/14 09/26/14 10/28/14 11/24/14 12/23/13 01/27/14 02/25/14 03/31/14 0

03/31/14 Ri 03/31/14 Ri 04/25/14 05/27/14 06/27/14 07/29/14 08/27/14 09/26/14 H-3 I 191 177 187 151 168 196 183 164 179 181 186 187 174 181 146 167 194 185 166 176 180 183 170 186 161 189 177 157 194 181 167 178 182 182 170 190 177 178 444 315 259 167 199 180 166 176 178 H-3 dginal ecount eanalysis

+ 135

+ 137

+ 136 B-6

LG-15-048, 2014 Annual Radiological Environmental Operating Report

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